JP2018004551A - Water supply equipment - Google Patents

Abstract

PROBLEM TO BE SOLVED: To provide water supply equipment capable of removing or reducing influences given to a user by a new radiation source formed by accumulation of radioactive materials contained in water.SOLUTION: Water supply equipment includes: a pump 131 the suction side of which is connected to a water receiving tank 120 and the discharge side of which is connected to a water supply pipe 130; a pressure sensor 901 for measuring a discharge side pressure of the pump; a radioactive material adsorption part 140 provided to a pipe 110 for supplying water to the water receiving tank; and a control part 40 which includes an input part from the pressure sensor, performs control of the pump, obtains a usage index of the water supply equipment, and performs determination related to a maintenance period of the radioactive material adsorption part on the basis of the usage index.SELECTED DRAWING: Figure 9

Description

  The present invention relates to a water supply facility.

  For example, when radioactive materials such as radioactive cesium and radioactive strontium diffuse around due to an accident at a nuclear power plant, it is necessary to remove those materials from tap water. An apparatus used for removing such a substance has a structure different from, for example, a conventional water purifier. Examples of such a device are described in Patent Document 1 and Patent Document 2, for example. The apparatus described in these documents is arrange | positioned near the faucet of water supply similarly to the conventional water purifier, for example.

JP 2013-7634 A JP 201421074 A

  However, as described in Patent Document 1 and Patent Document 2 above, when a device that removes radioactive substances from tap water is arranged near a tap, the removed radioactive substances are accumulated in the living space. Therefore, there is a possibility that the exposure of the user who uses this as a radiation source may occur. In addition, there is a water receiving tank that temporarily stores the supplied water and pipes in the building from the water main to the faucet, but the tap water is received in a state where radioactive materials are not removed. When passing through water tanks and pipes, radioactive substances accumulate in the water receiving tanks and pipes with the passage of time, and there is a possibility that users who use these as radiation sources will be exposed.

  The present invention has been made in view of the above points. One of the objects of the present invention is to eliminate or reduce the influence on a user of a new radiation source formed by accumulation of radioactive substances contained in water in a water supply facility including a radioactive substance adsorbing unit. It is to provide a new and improved water supply facility that is possible.

According to an aspect of the present invention, a pump having a suction side connected to a water receiving tank and a discharge side connected to a water supply pipe, a pressure sensor for measuring the discharge side pressure of the pump, and an introduction pipe for supplying water to the water receiving tank Equipped with a radioactive substance adsorbing unit and an input unit from the pressure sensor to control the pump, obtain the usage amount index of the water supply equipment, and determine the maintenance timing of the radioactive substance adsorbing unit based on the usage amount index A water supply facility including a control unit to be executed is provided.
According to another aspect of the present invention, a suction side connected to an introduction pipe communicating with a water supply source, a discharge side connected to a water supply pipe, a pressure sensor for measuring a discharge side pressure of the pump, and an introduction It has a radioactive substance adsorbing part provided in the pipe or the water supply pipe and an input part from the pressure sensor, and controls the pump, obtains the usage index of the water supply equipment, and based on the usage index, A water supply facility is provided that includes a control unit that performs a determination regarding a maintenance time.
In the water supply facility as described above, radioactive substances contained in water can be removed in the water supply system close to the water supply source. Therefore, by suppressing the accumulation of radioactive material in piping such as in a building, it is possible to eliminate or reduce the influence on the user of a new radiation source formed by the accumulated radioactive material. In such a water supply facility, the control unit can appropriately determine the maintenance timing of the radioactive substance adsorbing unit by using the usage amount index of the water supply facility. In addition, as also shown in the description of the embodiment described later, the water supply facility according to the embodiment of the present invention may be provided with a water receiving tank, such as a water main directly connected type without a water receiving tank. It may be a water supply facility.

The above usage index may include a cumulative flow rate in the introduction pipe or the water supply pipe. In this case, the cumulative flow rate may be calculated based on the number of rotations of the pump and the pressure measured by the pressure sensor.
For example, the accumulated flow rate in the water supply facility can be an effective index for appropriately determining the maintenance time of the radioactive substance adsorbing unit. In calculating the cumulative flow rate, it is particularly advantageous to use the number of revolutions of the pump and the pressure measured by the pressure sensor, for example when these values are already available for controlling the water supply. . In another example, the cumulative flow rate may be calculated based on a measured value of a separately provided sensor such as a flow meter.

The above usage index may include a cumulative operation time of the water supply facility. The control unit may further include an input unit of a radiation measurement sensor that measures the radiation dose of the water supply pipe, and the usage index may be the radiation dose of the water supply pipe.
For example, the cumulative operation time of the water supply facility can also be an effective index for appropriately determining the maintenance time of the radioactive substance adsorbing unit. The cumulative operation time may be used alone as a usage index, or may be used in combination with, for example, the above cumulative flow rate.

The above usage index can be reset when maintenance of the radioactive substance adsorbing unit is performed.
When maintenance of the radioactive substance adsorbing unit is performed, for example, the next maintenance timing of the radioactive substance adsorbing unit can be appropriately determined by resetting the usage amount index of the water supply facility.

The determination relating to the maintenance time includes determination of whether or not the usage amount index has reached the first threshold value, and the control unit determines that the maintenance time is determined when it is determined that the usage amount index has reached the first threshold value. An output unit configured to output information indicating that has arrived may be provided. The control unit has a second threshold value that is larger than the first threshold value, determines whether the usage amount index has reached the second threshold value, and if the usage amount index has reached the second threshold value, Water supply to the supply destination may be stopped. The water supply facility may further include a display unit that displays information indicating that a maintenance period has arrived or information regarding control of the pump. The control unit may further include a communication unit configured to transmit information indicating that the maintenance time has arrived or information regarding control of the pump to the external display. The communication unit may be a control unit side antenna unit that receives radio waves from an external display and converts the radio waves into electric power. The communication unit may transmit information to the external display device by near field communication (NFC).
By providing information indicating that the maintenance time has arrived to the administrator or the operator, prompt response can be promoted. The information may be provided via a display unit, or may be provided via an external display that has received the information through communication with a communication unit. The external display device may be, for example, a remote monitoring device, or may be a portable terminal device capable of communicating by near field communication (NFC) close to the water supply facility.

It is a figure showing roughly water supply equipment concerning a 1st embodiment of the present invention. It is a figure which shows roughly the water supply equipment which concerns on the 2nd Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 3rd Embodiment of this invention. It is a figure which shows roughly the water supply installation which concerns on the modification of the 3rd Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 4th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the modification of the 4th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the modification of the 5th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 6th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 1st example of the 7th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 2nd example of the 7th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 1st modification of the 7th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 2nd modification of the 7th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 3rd modification of the 7th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 8th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 1st modification of the 8th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 2nd modification of the 8th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 9th Embodiment of this invention. It is a figure which shows roughly the water supply equipment which concerns on the 10th Embodiment of this invention. It is a block diagram which shows the 1st structural example of the control part in each embodiment of this invention. It is a block diagram which shows the 2nd structural example of the control part in each embodiment of this invention. It is a figure which shows the modification of the control part shown in FIG. It is a figure for demonstrating the strainer which can be installed in each embodiment of this invention.

  Exemplary embodiments of the present invention will be described below in detail with reference to the accompanying drawings. In addition, about the component which has the same structure and function between different embodiment, the overlapping description may be abbreviate | omitted by attaching | subjecting a common code | symbol.

(First embodiment)
Drawing 1 is a figure showing roughly water supply equipment concerning a 1st embodiment of the present invention. Referring to FIG. 1, a water supply facility 100 includes an introduction pipe 110 connected to a water main 10 that is a water supply source, a water receiving tank 120 that stores water supplied from the introduction pipe 110, and a water receiving tank 120 that stores water. And a water supply pipe 130 for supplying the water to the water tap 20 which is a water demand destination. Furthermore, the water supply facility 100 includes a radioactive substance adsorbing unit 140 connected to the outlet of the introduction pipe 110 inside the water receiving tank 120. In the present embodiment, the radioactive substance adsorbing unit 140 is arranged so as not to be immersed in the water stored in the water receiving tank 120. More specifically, the radioactive substance adsorbing unit 140 is disposed above the attachment position of the overflow pipe 121 provided in the water receiving tank 120.

  The introduction pipe 110 is provided with a check valve 111 and an inflow valve 112. The check valve 111 prevents water once entering the introduction pipe 110 from flowing back to the water main pipe 10. The inflow valve 112 is controlled by the control unit 40 and adjusts the amount of water in the water receiving tank 120. More specifically, the inflow valve 112 is opened and closed according to the water level in the water receiving tank 120. A specific configuration example of the control unit 40 will be described later.

  Note that, as will be described later, in the water supply facility 100, pressure loss occurs in the radioactive substance adsorbing unit 140, so that the prevention of backflow by the check valve 111 as described above is effective. Thus, even if bacteria are attached or propagated in the radioactive substance adsorbing portion 140, it is possible to prevent the water main pipe 10 from being affected.

  The water receiving tank 120 is provided with an overflow pipe 121 and a water level gauge 122. The overflow pipe 121 is intended to prevent water from overflowing from the water receiving tank 120 when a failure occurs with the inflow valve 112 being opened. It can also be used to arrange so as not to be immersed in the water. In addition, for example, when the water level in the water receiving tank 120 can be reliably controlled to be in a state where the water level is reduced to a full level or less by controlling the inflow valve 112 and the pump 131, the radioactive material is used regardless of the presence and position of the overflow pipe 121. It may be possible to arrange the material adsorbing part 140 so as not to be immersed in water. The water level meter 122 detects the water level in the water receiving tank 120 using, for example, a plurality of electrode bars. The detected water level is used for controlling the inflow valve 112 and the pump 131 by the control unit 40. As an example, a method of detecting the water level of full, reduced, and drought using four electrode rods is shown. The inflow valve 112 is opened when the water level in the water receiving tank becomes lower than the reduced water level due to the water supply, and the inflow valve is closed when the water level becomes higher than the full water level. Further, in order to prevent the pump 131 from malfunctioning in the idling operation, the pump is forcibly stopped and water is cut off below the drought water level. The water level gauge 122 is not limited to the one having a plurality of electrode bars as shown in the figure. For example, a single electrode rod or a water level gauge with one or more float switches can be used. Alternatively, in the case where the water level in the water receiving tank 120 can be calculated based on the measured values of the flow meters provided in the introduction pipe 110 and the water supply pipe 130, the water level gauge 122 may not be provided.

  The water supply pipe 130 is provided with a pump 131. The pump 131 is driven by the motor 132 and the inverter 133 to supply water to the water tap 20. The pump 131 is controlled by the control unit 40 in the same manner as the inflow valve 112. More specifically, the control unit 40 controls the inverter 133, changes the rotation speed of the pump 131, and performs discharge pressure constant control or estimated terminal pressure constant control. In other embodiments, the inverter 133 is not provided, the pump is rotated at a fixed speed, the discharge pressure is made constant by a pressure reducing valve (not shown), or the control unit 40 causes the plurality of pumps 131 to be disconnected in parallel. Adjustment of the pressure may be realized.

  In addition, when the radioactive material adsorption part 140 is not provided in the water supply equipment, the water is supplied from the introduction pipe 110 to the water receiving tank 120 by opening the inflow valve 112 when the water level of the water receiving tank 120 becomes lower than the water level during the pump operation. In this case, the water receiving tank 120 having a capacity sufficient to restore the lowered water level in the water receiving tank 120 to full water is installed. However, in the water supply facility 100, when the radioactive substance adsorbing portion 140 connected to the outlet of the introduction pipe 110 is clogged with unexpected dust or the like, an excessive pressure loss occurs, so that the water supply from the introduction pipe 110 causes The recovery of the water level in the water receiving tank 120 may be delayed. If the water level does not recover even when the inflow valve 112 is opened and a certain amount of time has elapsed after the pump 131 is operating, the control unit 40 controls the number of rotations of the pump 131 to supply water to the faucet 20. Can be avoided by preventing the water receiving tank 120 from becoming drought.

The radioactive substance adsorption unit 140 includes, for example, a radioactive substance adsorption cartridge. The radioactive substance adsorbing cartridge is configured to be filled with a granular radioactive substance adsorbing material inside the housing. A water flow path is formed inside the housing so that the water supplied from the introduction pipe 110 efficiently passes through the radioactive substance adsorbent. Such a configuration filled with the granular radioactive material adsorbent can increase the adsorbent weight per volume, and is suitable for treating a large amount of water. However, instead of or in addition to the granular radioactive substance adsorbent, a cloth or activated carbon carrying the radioactive substance adsorbent may be used. In this case, since the reaction rate of the radioactive substance adsorbent is excellent, it is suitable for removing a low concentration radioactive substance. And when activated carbon is used, advantageous chlorine, odor, trihalomethane and the like can be removed from the water together with radioactive substances.

  Examples of radioactive material adsorbents include ion exchange resin, ion exchange fiber, chelate resin, chelate fiber, calcium alginate, chitosan, iron oxide, activated carbon, silver zeolite, silver phosphate, hydrotalcite, geopolymer, titanium oxide, silica gel, Preferably, at least one of amorphous aluminum silicate, zeolite, titanate, silicotitanate, manganese oxide, ferrocyanide, hydroxyapatite, cerium hydroxide, and zirconium hydroxide is included.

  For example, radioactive cesium is effectively adsorbed by using ion exchange resin, ion exchange fiber, zeolite, ferrocyanide, titanate, amorphous aluminum silicate, silicotitanate, etc. as a radioactive material adsorbent. be able to. Further, for example, as a radioactive material adsorbent, ion exchange resin, ion exchange fiber, chelate resin, chelate fiber, calcium alginate, chitosan, zeolite, titanate, amorphous aluminum silicate, silicotitanate, hydroxyapatite, geo By using a polymer or the like, radioactive strontium can be effectively adsorbed. Furthermore, adsorb radioactive iodine by using iron oxide, activated carbon, silver zeolite, silver phosphate, hydrotalcite, titanium oxide, silica gel, manganese oxide, cerium hydroxide, geopolymer, etc. as radioactive material adsorbents. Can do.

  As the radioactive material adsorbent, one type of adsorbent may be used, or a plurality of types of adsorbent may be used. For example, adsorbents that adsorb different radioactive substances may be mixed and used, or a plurality of types of adsorbents that adsorb a single radioactive substance may be mixed and used.

  Furthermore, for example, when titanate, amorphous aluminum silicate, silicotitanate or the like is used, radioactive cesium and radioactive strontium can be effectively removed simultaneously with a single adsorbent.

  It is known that the adsorption performance of ion exchange resins and zeolites that are cesium adsorbents decreases under conditions where the salt concentration is high. Similarly, iodine adsorbents are known to have poor adsorption performance under conditions of high salinity due to the similar chemical properties of iodine and chlorine. Further, the adsorption performance of the strontium adsorbent is also affected by the concentration of calcium or magnesium, and the adsorption performance is lowered under these high concentration conditions.

  Therefore, when contaminated water having a high concentration of salinity, calcium, or magnesium is to be treated, it is preferable to use an adsorbent with a small decrease in adsorption performance. Examples of such adsorbents include ferrocyanide and silicotitanate as radioactive cesium adsorbents. Examples of the radioactive strontium adsorbent include titanate and silicotitanate. Furthermore, examples of the radioactive iodine adsorbent include silver zeolite, silver phosphate, titanium oxide, manganese oxide, and cerium hydroxide.

  Among the radioactive material adsorbents, some adsorbents can remove heavy metals such as Pb, Cd, Hg, Zn, Cu, Ni, and Cr that are to be removed by the general water treatment. Further, Sb, As, Se, B, P, Si, white metal, etc., which are often in the form of oxo acid, can be removed.

In the water supply facility 100 that supplies drinking water, it is preferable to use a material that does not contain aluminum and aluminum compounds as the radioactive material adsorbent. In this way, it is possible to prevent aluminum that is suspected to be a cause of Alzheimer's disease from being contained in water.

  Further, the radioactive substance adsorbing unit 140 is provided with a radiation shielding structure 141 that shields radiation from the accumulated radioactive substance because the adsorbed radioactive substance is accumulated. For example, the radiation shielding structure 141 may cover the radioactive substance adsorbing unit 140 in the water receiving tank 120 as in the illustrated example, or may cover the entire water receiving tank 120 in another example.

  In the water supply equipment 100 configured as described above, the radioactive substance contained in the water is adsorbed by the radioactive substance adsorption unit 140 until the water flowing through the introduction pipe 110 is stored in the water receiving tank 120. Accordingly, the radioactive material does not reach the living space such as near the faucet of the water supply tap 20. Depending on the usage environment, the aquarium may generate algae and fallen leaves and garbage may enter. Also, rust is generated inside the building piping due to aging. Receiving tanks and piping in buildings may be used for a long period of 30 to 40 years. Supplying trace amounts of radioactive material in algae, fallen leaves, garbage, and rust in piping. Although water may be contaminated, the water stored in the water receiving tank 120 and the water flowing through the pipe in the building communicating with the water supply pipe 130 are also water after the radioactive material is adsorbed. There is no accumulation of radioactive material inside the piping in the building. Thus, in this embodiment, when removing a radioactive substance from the tap water supplied from the water main 10, the new radiation source formed when the radioactive substance contained in a tap water accumulates is a user. Can be removed or reduced.

  Moreover, in this embodiment, the radioactive substance adsorption | suction part 140 is arrange | positioned so that it may not be immersed in the water stored in the water receiving tank 120. FIG. As a result, for example, the outlet side of the radioactive substance adsorbing unit 140 is opened to the atmosphere. Therefore, when water is passed through the radioactive substance adsorbing unit 140, the pressure of the water supplied from the water main 10 is used to the maximum. can do. Further, since the outlet of the radioactive substance adsorption unit 140 is separated from the water stored in the water receiving tank 120, the radioactive substance adsorption unit 140 performs maintenance, specifically, exchange of the radioactive substance adsorption cartridge or the radioactive substance adsorption material. Therefore, even when it is in an unusable state, the control unit 40 only needs to close the inflow valve 112, and it is not necessary to drain the water stored in the water receiving tank 120. Further, while the inflow valve 112 is closed, it is possible to continue the water supply by operating the pump 131 as long as the water stored in the water receiving tank 120 remains.

  Usually, the water receiving tank 120 is installed outdoors. Therefore, the radioactive substance adsorption unit 140 is also installed outdoors. Thereby, compared with the case where it installs in a household, since there is room in installation space, the radioactive substance adsorption | suction part 140 can be enlarged. By increasing the size of the radioactive substance adsorbing portion 140, pressure loss can be reduced, or a large amount of water can be decontaminated at a time, so that there is an effect of preventing the water faucet 20 from running out of water. Further, the life of the radioactive substance adsorbing unit 140 can be extended, and the replacement frequency is reduced.

  In the present embodiment, the description has been given of the single tank type water receiving tank, but the same effect can be obtained by the two tank type water receiving tank system as shown in FIG. In that case, as shown in FIG. 10, the introduction pipe 110, the radioactive substance adsorption unit 140, the water receiving tank 120, and the water level sensor 122 are duplicated.

  The city water flow valve 112 is opened / closed only by a command from the control unit 40, but it may be opened / closed automatically by the water level of the water level sensor 122, or may be manually opened / closed. Good.

(Second Embodiment)
FIG. 2 is a diagram schematically showing a water supply facility according to the second embodiment of the present invention. Referring to FIG. 2, the water supply facility 200 includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. Furthermore, the water supply facility 200 includes a radioactive substance adsorbing unit 240 connected to the outlet of the introduction pipe 110 inside the water receiving tank 120. As a difference from the first embodiment, the radioactive substance adsorbing unit 240 is disposed so as to be immersed in water stored in the water receiving tank 120. About the point other than that, the structure of the radioactive substance adsorption | suction part 240 is the same as that of the radioactive substance adsorption | suction part 140 in said 1st Embodiment.

  In this embodiment, “arranged so that the radioactive substance adsorption unit 240 is immersed in the water stored in the water receiving tank 120” means that the radioactive substance adsorption unit 240 is always immersed in water. I don't mean. For example, when maintenance is performed on the water receiving tank 120 itself or the radioactive substance adsorbing unit 240, the water in the water receiving tank 120 may be discharged, and the radioactive substance adsorbing unit 240 may not be immersed in water. Further, even when the supply of water from the water main 10 is stopped or the water level of the water receiving tank 120 is not correctly adjusted due to a failure of the inflow valve 112, the pump 131, or the control unit 40, the radioactive material adsorption A state where the part 240 is not immersed in water may occur. That is, in the present embodiment, “the radioactive substance adsorbing unit 240 is disposed so as to be immersed in the water stored in the water receiving tank 120” means that the radioactive substance is in a state where the water supply facility 200 is operating normally. It means that the adsorption part 240 is immersed in water.

  Also in this embodiment, the radioactive substance contained in the water is adsorbed by the radioactive substance adsorbing unit 240 until the water flowing through the introduction pipe 110 is stored in the water receiving tank 120 as in the first embodiment. Is done. Therefore, the influence which the new radiation source formed when radioactive material contained in tap water accumulates like Example 1 has on a user can be removed or reduced. Moreover, in this embodiment, the radioactive substance adsorption | suction part 240 is arrange | positioned so that it may be immersed in the water stored in the water receiving tank 120. FIG. The radioactive substance adsorbing unit 240 accumulates the adsorbed radioactive substance, but since water shields the radiation, the radiation shielding structure is provided so as to cover the radioactive substance adsorbing part 140 in the first embodiment. Can be omitted or simpler.

  Usually, the water receiving tank 120 is installed outdoors. Therefore, the radioactive substance adsorbing unit 240 is also installed outdoors. Thereby, compared with the case where it installs in a household, since there is room in installation space, the radioactive substance adsorption | suction part 240 can be enlarged. By increasing the size of the radioactive substance adsorbing portion 240, pressure loss can be reduced and a large amount of water can be decontaminated at a time, so that there is an effect of preventing the water faucet 20 from running out of water. Further, the lifetime of the radioactive substance adsorbing portion 240 can be extended, and the replacement frequency is reduced.

(Third embodiment)
Drawing 3A is a figure showing roughly water supply equipment concerning a 3rd embodiment of the present invention. Referring to FIG. 3A, the water supply facility 300a includes an introduction pipe 310a, a water receiving tank 120, a water supply pipe 130, a control unit 40, and a radioactive substance adsorbing unit 340. In addition, since the structure of the water receiving tank 120, the water supply pipe 130, and the control part 40 is the same as that of said 1st Embodiment, the overlapping detailed description is abbreviate | omitted. The introduction pipe 310a is the same as the introduction pipe 110 in the first embodiment in that it is connected to the water main pipe 10 that is a water supply source and has a check valve 111 and an inflow valve 112. However, in this embodiment, the radioactive substance adsorbing part 340 is connected in the middle of the introduction pipe 310a. In the water supply facility 300a, the radioactive substance adsorbing unit 340 is connected to the introduction pipe 310a downstream of the inflow valve 112. In addition to the above arrangement, the configuration of the radioactive substance adsorption unit 340 is the same as that of the radioactive substance adsorption unit 140 in the first embodiment.

Also in this embodiment, the radioactive substance contained in the water is adsorbed by the radioactive substance adsorbing unit 340 until the water flowing through the introduction pipe 310a is stored in the water receiving tank 120, as in the first embodiment. Is done. Therefore, the influence which the new radiation source formed when radioactive material contained in tap water accumulates like Example 1 has on a user can be removed or reduced. In the present embodiment, unlike the other embodiments described above, the radioactive substance adsorbing portion 340 is provided in the introduction pipe 310a. Therefore, similarly to the first embodiment, the water stored in the water receiving tank 120 is used when performing maintenance such as replacement of the radioactive substance adsorbing cartridge or the radioactive substance adsorbing material of the radioactive substance adsorbing unit 340. It is possible to continue water supply. Furthermore, since it is not necessary for the worker to enter the water receiving tank 120 for maintenance, the maintenance work can be performed more simply and hygienically.

  Usually, the water receiving tank 120 is installed outdoors. Therefore, the radioactive substance adsorbing part 340 is also installed outdoors. Thereby, compared with the case where it installs in a household, since there is room in installation space, the radioactive substance adsorption | suction part 340 can be enlarged. By increasing the size of the radioactive substance adsorbing portion 340, pressure loss can be reduced, and a large amount of water can be decontaminated at a time, so that there is an effect of preventing the water faucet 20 from running out of water. Further, the lifetime of the radioactive substance adsorbing portion 340 can be extended, and the replacement frequency is reduced.

  Drawing 3B is a figure showing roughly water supply equipment concerning a modification of a 3rd embodiment of the present invention. Referring to FIG. 3B, the water supply facility 300 b includes an introduction pipe 310 b, a water receiving tank 120, a water supply pipe 130, a control unit 40, and a radioactive substance adsorption unit 340. The present modification is different from the water supply facility 300a described above in that the radioactive substance adsorbing unit 340 is connected to the introduction pipe 310b upstream of the inflow valve 112. In this case, the pressure applied to the radioactive substance adsorbing part 340 becomes substantially constant regardless of whether the inflow valve 112 is opened or closed, which is advantageous from the viewpoint of durability of the radioactive substance adsorbing part 340.

  In the water supply facility 300b, a maintenance valve 311 is provided in the introduction pipe 310b upstream of the radioactive substance adsorbing unit 340. The maintenance valve 311 is closed only during maintenance of the radioactive substance adsorbing unit 340, for example. Accordingly, the water flow passing through the radioactive substance adsorbing unit 340 is blocked, and maintenance of the radioactive substance adsorbing unit 340 becomes possible. In addition, as above-mentioned, in the water supply equipment 300a and said 1st and 2nd embodiment, the inflow valve 112 can function similarly to such a maintenance valve 311. The maintenance valve 311 may be provided upstream of the check valve 111.

(Fourth embodiment)
Drawing 4A is a figure showing roughly water supply equipment concerning a 4th embodiment of the present invention. Referring to FIG. 4A, the water supply facility 400a includes an introduction pipe 410a, a radioactive substance adsorption unit 420, a water supply pipe 430a, and a control unit 40. The introduction pipe 410a is connected to the water main pipe 10 which is a water supply source. The radioactive substance adsorbing unit 420 adsorbs a radioactive substance contained in water supplied from the introduction pipe 410a. The configuration of the radioactive substance adsorption unit 420 is the same as that of the radioactive substance adsorption unit 140 in the first embodiment except for the arrangement. The water supply pipe 430a is a pipe for supplying the water that has passed through the radioactive substance adsorbing unit 420 to the water tap 20 that is a water demand destination. As shown in the drawing, the water supply facility 400a is a water supply facility of a directly connected water supply system in which a water receiving tank is not provided unlike the other embodiments described above.

A backflow prevention device 411 is provided in the introduction pipe 410a. The backflow prevention device 411 prevents water once entering the introduction pipe 410 a from flowing back to the water main pipe 10. As illustrated, the introduction pipe 410a may further be provided with a maintenance valve 412. The maintenance valve 412 is closed only during maintenance of the radioactive substance adsorption unit 420, for example. Note that the maintenance valve 412 may be provided upstream of the check valve 411. Further, the introduction pipe 410 a is provided with a pressure sensor 413 that measures the pressure of the water main pipe 10.

  A pump 431 is provided in the water supply pipe 430a. The pump 431 is driven by the motor 432 and the inverter 433 and adjusts the pressure of water supplied to the water tap 20. The pump 431 is controlled by the control unit 40. More specifically, the control unit 40 determines that the pressure of the water main pipe 10 is equal to or higher than a certain value from the measured value of the inflow pressure sensor 413 indicating the pressure of the water main pipe 10, and is provided downstream of the pump 431. Based on the measured value of the discharge pressure sensor 434, the inverter 433 is controlled, and the rotation speed of the pump 431 is changed to perform the discharge pressure constant control or the estimated terminal pressure constant control. In other embodiments, the inverter 433 is not provided, the pump is rotated at a fixed speed, the discharge pressure is made constant by a pressure reducing valve (not shown), or the controller 40 additionally disconnects the plurality of pumps 432, Adjustment of the discharge pressure may be realized. Also, a bypass pipe (not shown) that bypasses the secondary side of the radioactive substance adsorbing section 420 and the pump 432 is provided, so that the water supply to the faucet 20 can be supplied without the pump 431 being operated because the pressure of the water main pipe 10 is high. If it can be ensured sufficiently, bypass water supply may be performed while the pump 431 is stopped.

  In the embodiment, since the inflow pressure sensor 413 and the discharge pressure sensor 434 are provided, the pressure loss between the inflow pressure sensor 413 and the discharge pressure sensor 434 can be measured. Specifically, the pressure loss occurs in the piping between the inflow pressure sensor 413 and the discharge pressure sensor 434, the backflow prevention device 411, the maintenance valve 412, the radioactive substance adsorption unit 420, and the pump 431. Here, when the radioactive substance adsorbing portion 420 is clogged with foreign matter and the pressure loss increases, the differential pressure between the inflow pressure sensor 413 and the discharge pressure sensor 434 increases. Therefore, when the pressure difference between the inflow pressure sensor 413 and the discharge pressure sensor 434 exceeds the threshold value, an alarm may be output from the control unit 40 on the assumption that the pressure loss of the radioactive substance adsorption unit 420 has increased. The control unit 40 may have a function of displaying the inflow pressure sensor 413 and the discharge pressure sensor 434. A specific configuration example of the control unit 40 will be described later.

  Note that the threshold value may be set so that the differential pressure between the inflow pressure sensor 413 and the discharge pressure sensor 434 is compared with the threshold value when the rotation speed of the pump 431 is at a certain frequency. Furthermore, immediately after the maintenance of the radioactive substance adsorbing unit 420 is completed, the pressure loss is minimized, and therefore, the differential pressure increase value is monitored using the differential pressure between the inflow pressure sensor 413 and the discharge pressure sensor 434 as a reference value. May be.

In the water supply facility 400 a configured as described above, in the water supply system close to the water main 10, the radioactive substance contained in the water is adsorbed by the radioactive substance adsorption unit 420. Therefore, the radioactive substance does not reach the living space such as near the faucet of the water tap 20. Moreover, since the water flowing through the in-building pipe communicating with the water supply pipe 430a is also the water after the radioactive substance is adsorbed, the radioactive substance does not accumulate inside the in-building pipe. Also, in condominiums and building commercial facilities where a direct water supply system is adopted, the pump 431 is usually installed in a pump room, machine room, or outdoors, so the radioactive substance adsorbing part 420 should also be installed in a place away from the living space. It becomes. Thus, also in this embodiment, when removing a radioactive substance from the tap water supplied from the water main 10, the radioactive substance which becomes a new radiation source formed by accumulation of the radioactive substance contained in the tap water The influence of the substance adsorbing unit 420 on the user of the supplied water can be removed or reduced.

Drawing 4B is a figure showing roughly water supply equipment concerning a modification of a 4th embodiment of the present invention. Referring to FIG. 4B, the water supply facility 400b includes an introduction pipe 410b, a radioactive substance adsorbing unit 420, and a water supply pipe 430b. This modification is different from the water supply facility 400a described above in that the pump 431 is provided not in the water supply pipe 430b but in the introduction pipe 410b. That is, in the water supply facility 400a, the radioactive substance adsorbing unit 420 is disposed upstream of the pump 431. However, in the water supply facility 400b according to the present modification, the radioactive substance adsorbing unit 420 is disposed downstream of the pump 431. For example, when a large pressure loss occurs in the radioactive substance adsorbing part 420 due to unexpected dust or the like, it is beneficial to arrange the radioactive substance adsorbing part 420 downstream of the pump 431 in order to secure the water pressure in the faucet 20. It can be. In this case, the pump 431 may have a function of a pressurizing pump that adjusts the pressure applied to the radioactive substance adsorbing unit 420 in addition to the function of adjusting the water pressure in the water tap 20. The pressurizing pump will be further described in a sixth embodiment to be described later.

  In the embodiment of the water supply facility 400b as well, as in the water supply facility 400a, the differential pressure between the inflow pressure sensor 413 and the discharge pressure sensor 434 is compared with a threshold value. An alarm may be output from the control unit 40, assuming that the pressure loss has increased. Further, like the water supply facility 400a, the control unit 40 may have a function of displaying the inflow pressure sensor 413 and the discharge pressure sensor 434. A specific configuration example of the control unit 40 will be described later.

(Fifth embodiment)
FIG. 5 is a diagram schematically showing a water supply facility according to the fifth embodiment of the present invention. Referring to FIG. 5, the water supply facility 500 includes an introduction pipe 510, a radioactive substance adsorption unit 520, a water supply pipe 530, and a control unit 40. The introduction pipe 510 is connected to the well 30 which is a water supply source. The radioactive substance adsorption unit 520 adsorbs a radioactive substance contained in water supplied from the introduction pipe 510. The configuration of the radioactive substance adsorption unit 520 is the same as that of the radioactive substance adsorption unit 140 in the first embodiment except for the arrangement. The water supply pipe 530 supplies water that has passed through the radioactive substance adsorbing unit 520 to the water tap 20 that is a water demand destination. As shown in the drawing, the water supply facility 500 is a water supply facility that uses the well 30 instead of the water main 10 as a water supply source, unlike the other embodiments described above.

  The introduction pipe 510 is provided with a pump 511. The pump 511 is driven by the motor 512 and the inverter 513 to pump water from the well 30 and adjust the amount of water supplied to the water tap 20 through the water supply pipe 530. The pump 511 is controlled by the control unit 40. More specifically, the control unit 40 controls the inverter 513 based on the measured value of the pressure sensor 534 installed on the downstream side of the pump 511, and changes the rotational speed of the pump 511. In other embodiments, the inverter 513 is not provided, the pump is rotated at a fixed speed, the discharge pressure is made constant by a pressure reducing valve (not shown), or the controller 40 additionally disconnects the plurality of pumps 511. Adjustment of the discharge pressure may be realized. Moreover, although the pump 511 is installed on land, it is good also as a submersible pump. When the pump 511 is a submersible pump, it is installed in the well 30. A specific configuration example of the control unit 40 will be described later.

  In this embodiment, the water supply facility 500 uses the well 30 as a water supply source. In such a case as well, as in the other embodiments described above, the radioactive substance contained in the supplied water is converted into the radioactive substance adsorbing unit 520. It is possible to prevent the radioactive material from reaching the vicinity of the faucet 20. When the water supply source is the well 30, it is considered that the supplied water is often agricultural water or industrial water rather than domestic water. In such a case, the water tap 20 is also used by the user. It will be located in space. Therefore, with the configuration of the water supply facility 500 as described above, it may be beneficial to remove or reduce the influence on the user of a new radiation source formed by accumulation of radioactive substances contained in well water.

(Sixth embodiment)
FIG. 6 is a diagram schematically showing a water supply facility according to the sixth embodiment of the present invention. Referring to FIG. 6, the water supply facility 600 includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. Further, the water supply facility 600 includes a pressurizing pump 601 provided in the introduction pipe 110 upstream of the radioactive substance adsorbing unit 140. In the illustrated example, a pressure pump 601 is provided in the introduction pipe 110 downstream of the inflow valve 112. In another example, the pressurizing pump 601 may be provided upstream of the inflow valve 112.

  The pressurizing pump 601 is driven by the motor 602 and the inverter 603 to adjust the pressure applied to the radioactive substance adsorbing unit 140. The pressurizing pump 601 is controlled by the control unit 40 in the same manner as the inflow valve 112. More specifically, the control unit 40 controls the inverter 603 based on the measured value of the pressure sensor 604 provided on the primary side of the radioactive substance adsorbing unit 140 and changes the rotation speed of the pressurizing pump 601. The discharge pressure constant control or the estimated terminal pressure constant control is performed. In another embodiment, the inverter 603 is not provided, the pump is rotated at a fixed speed, the discharge pressure is made constant by a pressure reducing valve (not shown), or the controller 40 additionally disconnects the plurality of pumps 432, Adjustment of the discharge pressure may be realized.

  Note that when the supply of water via the inlet pipe 110 is blocked by the inflow valve 112, the pressurizing pump 601 is also stopped. More specifically, the controller 40 controls the opening and closing of the inflow valve 112 by the water level 122 of the water receiving tank 120 as described in the first embodiment. When the control for closing the inflow valve 112 is executed, the pressurization pump 601 is stopped, and when the control for opening the inflow valve 112 is executed, the control for operating the pressurization pump 601 is also executed.

  For example, when the pressure of the water supplied from the water main 10 is low and the pressure pump 601 may reduce the amount of water supplied to the water receiving tank 120 due to the pressure loss generated in the radioactive material adsorption unit 140. Provided. In this case, the control unit 40 controls the pressurizing pump 601 so that a sufficiently high pressure is indicated by the measurement value of the pressure sensor 604. In this case, since the water that has passed through the radioactive substance adsorbing unit 140 is stored in the water receiving tank 120, the pressure fluctuation can be allowed as long as it is within the allowable range of the radioactive substance adsorbing unit 140. Therefore, as the simplest configuration, the pressure adjustment may be realized by the control unit 40 controlling the motor 602 to operate / stop the single pressurizing pump 601.

  Further, for example, the adjustment of the pressure by the pressurizing pump 601 may be performed in order to reduce the damage caused by the fluctuation of the pressure on the radioactive substance adsorbing unit 140. In this case, the control unit 40 may control the pressurizing pump 601 so that the pressure applied to the radioactive substance adsorbing unit 140 becomes uniform, that is, the pressure approaches a predetermined value, for example. More specifically, the control unit 40 controls the rotation speed of the pressurizing pump 601 so that the measurement value of the pressure sensor 604 approaches a predetermined value. As a result, for example, when the pressure of water supplied from the water main 10 is increased, the rotation speed of the pressurizing pump 601 is decreased. Moreover, when the pressure of the water supplied from the water main 10 decreases, the rotation speed of the pressurizing pump 601 increases.

  In addition to or in place of the control for homogenization as described above, the control unit 40 smoothes the pressure applied to the radioactive substance adsorbing unit 140, that is, pressurizes the pressure pump 601 so as to alleviate the change in pressure. May be controlled. More specifically, for example, when the closed inflow valve 112 is opened and the supply of water via the introduction pipe 110 is started or restarted, the control unit 40 rapidly increases the rotation speed of the pressurizing pump 601. Increase gradually rather than to. Similarly, when the pressure of the water main pipe 10 fluctuates rapidly, the control unit 40 controls the rotation speed of the pressurizing pump 601 so as to follow the change with a delay. As a result, the pressure applied to the radioactive substance adsorbing part 140 gradually increases or decreases, and damage (for example, the cloth carrying the radioactive substance adsorbing material is torn) caused by the fluctuation of the pressure is given to the radioactive substance adsorbing part 140. Can be reduced.

In this embodiment, by providing the pressurizing pump 601, for example, the radioactive substance adsorption unit 1
The pressure applied to 40 can be maintained, or the damage caused to the radioactive substance adsorbing part 140 by fluctuations in pressure can be reduced. For example, as in the first to fifth embodiments, when a radioactive substance adsorbing unit is provided in a water supply system close to a water supply source to adsorb the radioactive substance, the pressure loss in the radioactive substance adsorbing part, or the radioactive substance Although the influence of the fluctuation of the pressure applied to the adsorption part may occur, in this embodiment, by providing the pressurizing pump 601, these influences are dealt with, and the radioactive substance adsorption part 140 can stably remove the radioactive substance, Stable water supply to the water receiving tank can be realized.

  In addition, although the water supply equipment 600 which concerns on this embodiment was demonstrated as what provided the pressurization pump 601 in the water supply equipment 100 which concerns on 1st Embodiment, the effect of the pressurization pump 601 is provided with a water receiving tank. Other configurations of the water supply facility, such as the second and third embodiments, can be similarly obtained. In other words, as a modification of the present embodiment, in the water supply facility 200 shown in FIG. 2, the pressurizing pump 601 may be provided in the introduction pipe 110 upstream of the radioactive substance adsorbing unit 240. Similarly, in the water supply facility 300a shown in FIG. 3A, the pressurizing pump 601 may be provided in the introduction pipe 310a upstream of the radioactive substance adsorbing unit 340. In the water supply facility 300b shown in FIG. 3B, the pressurizing pump 601 may be provided in the introduction pipe 310b upstream of the radioactive substance adsorbing unit 340. In the water supply facility 400a shown in FIG. 4A, a pressurizing pump 601 may be provided in the introduction pipe 410a upstream of the radioactive substance adsorption unit 420. Moreover, in the water supply equipment 400b shown in FIG. 4B as a modification of the fourth embodiment, a pump 431 is provided upstream of the radioactive substance adsorbing section 420. In the water supply facility 500 shown in FIG. 5 as the fifth embodiment, a pump 511 is provided upstream of the radioactive substance adsorbing unit 520. These pumps 431 and 511 can also have the same function as the pressurizing pump 601 of this embodiment.

(Seventh embodiment)
Drawing 7A is a figure showing roughly water supply equipment concerning the 1st example of a 7th embodiment of the present invention. Referring to FIG. 7A, the water supply facility 700 a includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. Furthermore, the water supply facility 700 a includes a radiation measurement sensor 701 provided in the radioactive substance adsorption unit 140. In this embodiment, the control part 40 detects the state regarding the water supply equipment 700a based on the measured value of the radiation measurement sensor 701. Moreover, the control part 40 may be provided with the alerting | reporting device 710 for reporting an alarm and abnormality based on a detection result. A specific configuration example of the control unit 40 will be described later.

  An example of state detection by the control unit 40 and control based on the detection result will be described below. For example, the control part 40 detects the 1st state which generate | occur | produced in the water supply equipment 700a, when the measurement dose of the radiation measurement sensor 701 exceeds a threshold value. Control part 40 which detected the 1st state continues water supply, outputting an alarm. Further, when the measurement dose of the radiation measurement sensor 701 increases (second state), for example, the inflow valve 112 is closed and the supply of water via the introduction pipe 110 is shut off. Alternatively, the control unit 40 may stop the pump 131 and substantially stop the supply of water to the water tap 20 via the water supply pipe 130.

Here, the first state includes, for example, a state in which the accumulation of the radioactive substance in the radioactive substance adsorbing unit 140 reaches a predetermined level. As the radioactive substance adsorbed on the radioactive substance adsorption unit 140 is accumulated, the measurement dose of the radiation measurement sensor 701 increases. Therefore, if the measurement dose of the radiation measurement sensor 701 becomes a certain level or more, for example, the radioactive substance accumulated in the radioactive substance adsorption unit 140 increases, and maintenance such as replacement of the radioactive substance adsorption cartridge or the radioactive substance adsorption material is necessary. That you have reached the correct level. In such a case, if the water supplied from the introduction pipe 110 continues to pass through the radioactive substance adsorption unit 140, the measurement dose of the radiation measurement sensor 701 further increases and the second threshold (second threshold ≧ first Threshold) is exceeded (second state). In the second state, there is a possibility that high-dose water is supplied to the faucet 20 without being absorbed by the radioactive substance adsorbing unit 140, or the maintenance of the radioactive substance adsorbing unit 140 is hindered. More specifically, wearing radiation protective clothing for maintenance work, the dose of the radioactive material adsorption cartridge or radioactive material adsorbent after replacement exceeds the reference value, it becomes radioactive waste, making disposal difficult, In the worst case, workers may be exposed during maintenance work. Therefore, when the measurement dose of the radiation measurement sensor 701 exceeds the second threshold, the control unit 40 detects the second state and stops the supply of water, and more radioactive material accumulates in the radioactive material adsorption unit 140. It can be beneficial not to do so.

  Note that since the measurement dose of the radiation measurement sensor generally includes an error such as background noise, it is not always appropriate to directly compare the measurement value of the radiation measurement sensor 701 with the threshold value. Therefore, for example, when the measurement value of the radiation measurement sensor 701 becomes a reference (for example, at the start of use of the radioactive substance adsorption unit 140 or when the radioactive substance adsorption cartridge or the radioactive substance adsorbent is replaced), the initial measurement dose The first state and the second state may be detected using the increase rate or the increase width with respect to the reference value.

In the water supply facility 700a as described above, the radiation measurement sensor 701 is installed in the vicinity of the radioactive substance adsorption unit 140, and the dose of the radioactive substance adsorption unit 140 is measured. This measured dose is acquired by the control unit 40.
When the measurement dose of the radiation measurement sensor 701 is equal to or higher than the first threshold (eg, 30% or more of the dose at which the radioactive substance adsorbing unit 140 becomes radioactive waste), the control unit 40 outputs a radiation dose warning and outputs the radioactive substance. Exchange of the suction unit 140 is urged. At this time, the opening / closing control of the inflow valve 112 and the control of the pump 131 are performed in the same manner as in the normal state, and water supply is continued (first state). Further, when the measurement dose of the radiation measurement sensor 701 increases and becomes equal to or higher than the second threshold (eg, 50% or more of the dose at which the radioactive substance adsorbing unit 140 becomes radioactive waste), the control unit 40 generates a radiation dose abnormality. Report (second state). In this second state, the control unit 40 forcibly closes the inflow valve 112 to prevent contamination of the water receiving tank 120, the pump 131, and the water supply pipe 130, and notifies the abnormality from the alarm 710. When the inflow valve 112 is forcibly closed, the supply of water from the water main 10 to the water receiving tank 120 is stopped. Therefore, the water stored in the water receiving tank 120 when the inflow valve 112 is forcibly closed can be supplied to the faucet 20, but it is received when the operation of the pump 131 is continued while the inflow valve 112 is forcibly closed. The water level in the water tank 120 is lowered, and as a result, the pump 131 is stopped by a drought warning.

  As an example of the first threshold value and the second threshold value in the present embodiment, the dose at which the radioactive substance adsorption unit 140 becomes radioactive waste is used as a reference, but the maximum dose that can be adsorbed by the radioactive substance adsorption unit 140 is used as a reference. Alternatively, the threshold dose may be determined based on the lower of the dose that becomes radioactive waste or the maximum dose that can be adsorbed. Furthermore, in addition to the detection of the first state and the second state by the radiation dose described above, the usage period of the radioactive substance adsorption cartridge or the radioactive substance adsorbent is measured, and the usage period exceeds a certain period. The first state and the second state may be detected. Then, even if the radiation measurement sensor 701 breaks down, the first state and the second state can be detected.

In the second state where the radiation dose of the radioactive substance adsorbing unit 140 is estimated to be very high, there is a risk of being exposed to radiation when approaching the water supply facility 700a. Therefore, a notification that enables the second state to be recognized remotely without being on the machine side is effective. Therefore, the indicator 710 may use an indicator lamp, a buzzer, a siren or the like that can be confirmed even from a place several meters away. Furthermore, you may install the alerting | reporting device 710 in a manager's room, a residence room, etc. so that the raise of a radiation dose can be confirmed in the place away from the water supply equipment 700a. The alarm 710 may also notify the first state.

  Drawing 7B is a figure showing roughly water supply equipment concerning the 2nd example of a 7th embodiment of the present invention. Referring to FIG. 7B, the water supply facility 700 b includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. Further, the water supply facility 700 b includes a first radiation measurement sensor 701 provided in the radioactive substance adsorbing unit 140 and a second radiation measurement sensor 702 provided in the water supply pipe 130. In this embodiment, the control part 40 detects the state regarding the water supply equipment 700b based on the measured value of the 1st radiation measurement sensor 701 and / or the 2nd radiation measurement sensor 702. In the illustrated example, the control unit 40 controls the inflow valve 112 or the pump 131 based on the detection result. A specific configuration example of the control unit 40 will be described later.

  An example of state detection by the control unit 40 and control based on the detection result will be described below. For example, the control unit 40 determines the first state generated in the water supply facility 700b when the measurement value of either the first radiation measurement sensor 701 or the second radiation measurement sensor 702 exceeds the first threshold value. To detect. Control part 40 which detected the 1st state continues water supply, outputting an alarm. Further, when the measured dose of the first radiation measurement sensor 701 and / or the second radiation measurement sensor 702 rises above the second threshold (second state), for example, the inflow valve 112 is closed and the introduction pipe 110 is passed. Shut off water supply. Alternatively, the control unit 40 may stop the pump 131 and substantially stop the supply of water to the water supply terminal 20 via the water supply pipe 130.

  Here, the first state includes, for example, a state in which radioactive substance accumulation in the radioactive substance adsorbing unit 140 reaches a predetermined level. The measurement dose of the first radiation measurement sensor 701 increases as the radioactive substance adsorbed on the radioactive substance adsorption unit 140 is accumulated. Therefore, if the measurement value of the first radiation measurement sensor 701 exceeds the first threshold value, for example, the radioactive substance accumulated in the radioactive substance adsorbing unit 140 increases and the radioactive substance adsorption cartridge or the radioactive substance adsorbent is replaced. That the required level of maintenance has been reached. In such a case, if the water supplied from the introduction pipe 110 continues to pass through the radioactive substance adsorption unit 140, the measurement dose of the radiation measurement sensor 701 further increases and the second threshold (second threshold ≧ first Threshold) is exceeded (second state). In the second state, the radioactive substance adsorbing unit 140 may not be able to adsorb, and there is a possibility that high-dose water is supplied to the faucet 20 or the radioactive substance adsorbing part 140 maintenance is hindered. More specifically, wearing radiation protective clothing for maintenance work, the dose of the radioactive material adsorption cartridge or radioactive material adsorbent after replacement exceeds the reference value, it becomes radioactive waste, making disposal difficult, In the worst case, workers may be exposed during maintenance work. Therefore, when the measurement value of the first radiation measurement sensor 701 exceeds the second threshold value, the control unit 40 detects the second state and stops the supply of water, and the radioactive substance adsorbing unit 140 is further radioactive. It can be beneficial to prevent substances from accumulating.

Moreover, said 1st state includes the state where the radioactive substance density | concentration of the water supplied to the water supply terminal 20 is rising, for example. As for the second radiation measurement sensor 702, as long as the radioactive substance is normally adsorbed by the radioactive substance adsorption unit 140, the measurement value should indicate that the radiation is not substantially detected. However, when the radioactive substance adsorption cartridge 140 of the radioactive substance adsorbing unit 140 or the radioactive substance adsorbing material is damaged, for example, when the radioactive substance adsorbing capability of the radioactive substance adsorbing unit 140 is reduced or lost, the water passing through the water supply pipe 130 is lost. Radiation dose increases. For example, even if the radioactive substance adsorbing unit 140 is functioning normally, if the concentration of radioactive substance in the water supplied from the water main pipe 10 has risen abnormally and cannot be removed, the water supply pipe 130 is similarly connected. The concentration of radioactive material in the passing water increases. In these cases, since the measured dose of the second radioactive sensor 702 increases, it may be beneficial for the control unit 40 to detect the second state and stop the supply of water based on this.

  In the present embodiment, the control unit 40 not only performs threshold determination for each measurement value of the first radiation measurement sensor 701 and the second radiation measurement sensor 702 as described above, but also performs both measurements. A combination of values may be used. For example, the control unit 40 may treat the measurement value of the second radiation measurement sensor 702 indicating that radiation is not substantially detected when normal, as indicating background noise caused by natural radiation or the like. In this case, for example, the control unit 40 may perform the threshold determination after subtracting the measurement dose of the second radiation measurement sensor 702 from the measurement dose of the first radiation measurement sensor 701.

  Further, since at least some radioactive substance is accumulated in the used radioactive substance adsorbing unit 140, the measured value of the first radiation measurement sensor 701 is the start of use of the radioactive substance adsorbing part 140 or the radioactive substance adsorbing cartridge. Or it should always be higher than the measured value of the 2nd radiation measurement sensor 702 except for immediately after replacement | exchange of a radioactive substance adsorbent. Therefore, for example, when the measurement value of the second radiation measurement sensor 702 exceeds the measurement value of the first radiation measurement sensor 701, the control unit 40 has failed in a portion related to any one of the sensors. A state may be detected. Also in this case, it is conceivable that the inflow valve 112 is shut off as described above, the pump 131 is stopped, or a notification is output as in a modified example described later.

  Since the measurement values of the radiation measurement sensor generally include an error, the measurement values of the first radiation measurement sensor 701 and the second radiation measurement sensor 702 are directly compared with the first or second threshold, It is not always appropriate to compare with each other. Therefore, for example, the measured value of each radiation measurement sensor is a reference value (for example, at the start of use of the radioactive substance adsorbing unit 140 or when the radioactive substance adsorption cartridge or the radioactive substance adsorbent is replaced). It may be recorded as an initial reference value, and the first state and the second state may be detected using an increase rate or an increase width with respect to the reference value.

  As in the first example of the present embodiment described above, the first threshold value and the second threshold value in the present example are the dose at which the radioactive substance adsorbing unit 140 becomes radioactive waste or the radioactive substance adsorbing unit 140. The maximum dose that can be absorbed may be used as a reference. Further, the threshold dose may be determined based on the lower of the dose that becomes radioactive waste or the maximum dose that can be adsorbed. Furthermore, in addition to the detection of the first state and the second state by the radiation dose described above, the usage period of the radioactive substance adsorption cartridge or the radioactive substance adsorbent is measured, and the usage period exceeds a certain period. The first state and the second state may be detected. Then, even if the radiation measurement sensor 701 breaks down, the first state and the second state can be detected. Each threshold value in the first radiation measurement sensor 701 and the second radiation measurement sensor 702 may be set individually.

  In this embodiment, since the radiation dose of the water supplied to the faucet is measured by the measured dose of the second radioactive sensor 702, there is no problem if the dose of the second radioactive sensor 702 is normal. Therefore, the first radioactive sensor 701 may be omitted. In that case, the first state and the second state described above are detected only by the second radioactive sensor 702. Then, it is possible to make one radiation sensor.

Furthermore, in the first example and the second example of the embodiment, the radiation dose of the radioactive material adsorbing portion 140 of the water flowing into the water receiving tank 120 is measured, but this will be described with reference to FIGS. 4A, 4B, and 5. Even in a water supply facility (direct connection type) that directly connects the primary side of the pump to a supply source without a water receiving tank, measurement of the dose of the radioactive substance adsorbing part 420 and the radioactive substance adsorbing part 450 and a radiation dose alarm (detection of the first state) ) Notification of radiation dose alarm abnormality (detection of the second state) is effective as in this embodiment. However, in the direct connection type, when the radiation dose abnormality is reported (the second state is detected), the pump operation may be disabled immediately.

  Drawing 7C is a figure showing roughly water supply equipment concerning the 1st modification of a 7th embodiment of the present invention. Referring to FIG. 7C, the water supply facility 700 c includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. In addition, the water supply facility 700c includes a first radiation measurement sensor 701 and a second radiation measurement sensor 702, similarly to the water supply facility 700b described above. A water supply facility 700c according to the present modification is different from the water supply facility 700b described above in that the control unit 40 includes an output unit (described later) such as a display unit.

  In this modification, the output unit of the control unit 40 outputs a notification directed to the administrator or operator of the water supply facility 700c based on the detection result. More specifically, for example, the output unit has a radioactive substance adsorbing unit as the first state when the measurement value of the first radiation measurement sensor 701 or the second radiation measurement sensor 702 exceeds the first threshold value. A notification urging maintenance such as replacement of the radioactive substance adsorption cartridge 140 or the radioactive substance adsorbent may be output. In addition, for example, the output unit has a measurement dose of the second radiation measurement sensor 702 that exceeds the first threshold value, or a measurement dose of the second radiation measurement sensor 702 exceeds a measurement value of the first radiation measurement sensor 701. In such a case, a notification urging inspection of the water supply facility 700c including these radiation measurement sensors may be output.

  Also in this modification, the control unit 40 may control the inflow valve 112 or the pump 131 based on the detection result, similarly to the water supply facility 700b. In this case, the control of the inflow valve 112 or the pump 131 by the control unit 40 may be performed simultaneously with the notification output by the output unit as described above, or may be performed in stages in combination with the notification output. . For example, when the measurement dose of either the first radiation measurement sensor 701 or the second radiation measurement sensor 702 exceeds the first threshold, the control unit 40 generates the first radiation generated in the radioactive substance adsorption unit 140. Detect state. At this time, the output unit may output a notification urging maintenance of the radioactive substance adsorbing unit 140 or inspection of the water supply facility 700b to continue water supply. Furthermore, the control unit 40 adsorbs the radioactive substance when the measurement value of either the first radiation measurement sensor 701 or the second radiation measurement sensor 702 exceeds a second threshold value that is larger than the first threshold value. A more serious second state occurring in the unit 140 is detected. At this time, the control unit 40 may close or substantially stop the supply of water by closing the inflow valve 112 or stopping the pump 131.

  Drawing 7D is a figure showing roughly water supply equipment concerning the 2nd modification of a 7th embodiment of the present invention. Referring to FIG. 7D, the water supply facility 700 d includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. In addition, the water supply facility 700d includes a first radiation measurement sensor 701 and a second radiation measurement sensor 702, similarly to the water supply facility 700b described above. This modified example is different from the water supply facility 700b described above in that the control unit 40 includes a communication unit (described later). The communication unit communicates with the remote monitoring device 707 via a network 706 such as the Internet or a dedicated line. The display operation unit of the remote monitoring device 707 and the control unit 40 includes, for example, a display or lamp that outputs a visual notification, or a speaker, siren, or buzzer that outputs an audible notification, and their control circuits. Including an output unit. Alternatively, as described later, the communication unit may communicate with an external display device by NFC (Near Field Communication) or the like, and the external display device may output a notification.

In the second state where the radiation dose of the radioactive substance adsorbing unit 140 is very high, the radioactive substance adsorbing unit 140 is exposed to an explosion when approaching the water supply facility 700d. Therefore, the notification via the network that can be recognized remotely from the control unit 40 is effective. Further, when the water supply facility 700d is installed in a pump room or outdoors, a remote monitoring device 707 that can confirm an increase in radiation dose in a manager's room or a living room may be provided.

  The control unit 40 provides detection results of the first state and the second state to the remote monitoring device 707 via the communication unit and the network 706. The remote monitoring device 707 can output a notification for an administrator or an operator who is away from the water supply facility 700d based on the detection result. The content of the notification can be the same as the notification output from the output unit in the water supply facility 700b, for example. That is, the remote monitoring device 707 can output a notification that prompts maintenance of the radioactive substance adsorbing unit 140 or a notification that prompts inspection of the water supply facility 700 c based on the detection result of the control unit 40. The communication unit may transmit information indicating the measurement value of the first radiation measurement sensor 701 or the second radiation measurement sensor 702 to the remote monitoring device 707 together with the detection result or instead of the detection result. This information may be, for example, the measurement value itself, or information processed so that the measurement value can be easily used. The information processed in this way may include a value indicating background noise, for example, a value obtained by subtracting a measurement value of the second radiation measurement sensor 702 from a measurement value of the first radiation measurement sensor 701. Here, the measurement value is not necessarily the measurement value itself of each radiation measurement sensor, but the increase rate or the increase width with respect to the reference value may be treated as the measurement value as described above.

  Also in this modification, the control unit 40 may control the inflow valve 112 or the pump 131 based on the detection result, similarly to the water supply facility 700b. In this case, the control of the inflow valve 112 or the pump 131 by the control unit 40 may be performed simultaneously with the output of the notification by the remote monitoring device 707 as described above, or is performed stepwise in combination with the output of the notification. Also good. In addition, the remote monitoring device 707 further includes an input unit including, for example, a button, a lever, a keyboard, a mouse, or a touch panel, and the administrator who refers to the notification provided by the output unit or the measurement value of the radiation measurement sensor or An operator's operation may be accepted. In this case, the communication unit may receive an operation signal transmitted from the remote monitoring device 707 via the network 706, and the control unit 40 may control the inflow valve or the pump 131 according to the operation signal received by the communication unit. Accordingly, for example, the controller 40 or the operator who receives the notification may cause the control unit 40 to control the inflow valve 112 or the pump 131 based on an operation given to the remote monitoring device 707 to temporarily stop water supply. It becomes possible. In particular, when the radiation dose is high, there is a high possibility of being exposed even if it is close to 700d. Therefore, it is effective to monitor the radiation dose with the remote monitoring device 707.

  In addition, the remote monitoring device 707 acquires the measurement dose result of the first radiation measurement sensor 701 or the second radiation measurement sensor 702 in the water supply facility 700d to be monitored via the communication unit and the network 706, and the first state Alternatively, the second state may be determined. By doing so, the first threshold value and the second threshold value of all the water supply facilities 700d monitored by the remote monitoring device 707 can be managed in an integrated manner.

  FIG. 7E is a diagram schematically showing a water supply facility according to a third modification of the seventh embodiment of the present invention. Referring to FIG. 7E, the water supply facility 700e includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorbing unit 140, and a control unit 40. In addition, the water supply facility 700e includes a first radiation measurement sensor 701 and a second radiation measurement sensor 702, similarly to the water supply facility 700b described above. This modification is different from the water supply facility 700b described above in that the water supply facility 700e further includes a third radiation measurement sensor 708. In the water supply facility 700d, the control unit 40, based on the measurement values of the third radiation measurement sensor 708, in addition to the measurement values of the first radiation measurement sensor 701 and the second radiation measurement sensor 702, 140 states are detected.

Here, the third radiation measurement sensor 708 is disposed in the atmosphere outside the water supply system including the introduction pipe 110, the water receiving tank 120, and the water supply pipe 130. Therefore, the control unit 40 can treat the measurement value of the third radiation measurement sensor 708 as indicating background noise caused by natural radiation or the like. In the water supply facility 700b described above, it has been described that the measurement value of the second radiation measurement sensor 702 may be treated as indicating background noise when normal. However, for example, when some abnormality occurs and the radioactive substance concentration of the water flowing through the water supply pipe 130 increases, the measurement value of the second radiation measurement sensor also increases and can no longer be treated as background noise. The measurement value of the third radiation measurement sensor 708 can be treated as indicating background noise even in such a case. That is, in the present modification, by providing the third radiation measurement sensor 708, it is possible to use data with higher availability that indicates background noise. The third radiation measurement sensor 708 is used as a detection mechanism in the event that radiation leaks outside the water supply facility in addition to being used for obtaining a measurement value indicating background noise as described above. It can also be used.

  In addition, the structure of the water supply equipment 700b-700d which concerns on this embodiment demonstrated above and its modification is mutually combinable. For example, as already described, even in the water supply facility 700c in which the notification is output by the output unit and the water supply facility 700d in which the notification is output by the remote monitoring device 707, the control unit 40 of the control unit 40 together with the output of the notification. The inflow valve 112 or the pump 131 may be controlled based on the detection result. In the water supply facility, both an output unit, a communication unit, and a remote monitoring device 707 may be provided. In this case, for example, a notification may be output from both the output unit and the remote monitoring device 707. Alternatively, whether to output the notification from the output unit or the remote monitoring device 707 may be selected according to the location of the administrator or operator, the urgency of the notification content, or the like. Moreover, you may provide the alerting | reporting device 710 in the control part 40 of the water supply equipment 700b-700d similarly to 700a. Further, the third radiation measurement sensor 708 may be provided in the water supply facility 700b, the water supply facility 700c, or the water supply facility 700d.

  In the present embodiment, by providing the radiation measurement sensors 701 and 702 and the control unit 40, a state relating to the water supply facilities 700b to 700d, for example, a state in which radioactive substance accumulation in the radioactive substance adsorbing part 140 has reached a predetermined level, Alternatively, it is possible to detect a state where the radioactive substance concentration of water supplied to the water tap 20 is increasing. When such a state is detected, the control part 40 can control the inflow valve 112 or the pump 131, and can stop water supply. In addition, information regarding the detected state, for example, maintenance of the radioactive substance adsorbing unit 140 or notification for prompting inspection of the water supply facilities 700b to 700 can be output via the output unit or the communication unit. As a result, in the present embodiment, it is possible to cope with various states that may occur in the water supply facilities 700b to 700d in relation to the removal of the radioactive substance earlier.

  In addition, although the water supply equipment 700b-700d which concerns on this embodiment was demonstrated as what provided the radiation measurement sensor 701,702 and the control part 40 in the water supply equipment 100 which concerns on 1st Embodiment, of these component elements The effect can be similarly obtained in other configurations of the water supply facility in which the water receiving tank is provided, for example, the second and third embodiments. That is, as a modification of the present embodiment, in the water supply facility 200 shown in FIG. 2, a radiation measurement sensor is provided in each of the radioactive substance adsorbing unit 240 and the water supply pipe 130, and a control unit that uses the measurement values of these sensors. May be provided. Similarly, in the water supply facilities 300a and 300b shown in FIGS. 3A and 3B, the radioactive substance adsorption unit 340 and the water supply pipe 130 are provided with radiation measurement sensors, respectively, and a control unit that uses the measurement values of these sensors is provided. May be.

Furthermore, the modification of this embodiment can also include a directly-connected water supply system in which a water receiving tank is not provided. That is, even when a radioactive substance adsorbing unit is provided in a directly-coupled water supply system, it is possible to adopt the same configuration as the radiation measurement sensors 701 and 702 and the control unit 40 in the present embodiment. More specifically, for example, in the water supply facilities 400a and 400b according to the fourth embodiment described above with reference to FIGS. 4A and 4B, radiation is applied to the radioactive substance adsorbing part 420 and the water supply pipes 430a and 430b, respectively. A measurement sensor may be provided, and a control unit that uses the measurement values of these sensors may be provided. Similarly, in the water supply facility 500 according to the fifth embodiment described above with reference to FIG. 5, radiation measurement sensors are provided in the radioactive substance adsorbing unit 520 and the water supply pipe 530, respectively, and measured values of these sensors are provided. You may provide the control part which utilizes.

  Further, the modification of the present embodiment may be a modification of the sixth embodiment. That is, in the water supply facility described above as the present embodiment or the modification thereof, a pressurizing pump as described in the sixth embodiment may be provided in addition to the radiation measurement sensor and the control unit.

(Eighth embodiment)
FIG. 8A is a diagram schematically showing a water supply facility according to an eighth embodiment of the present invention. Referring to FIG. 8A, the water supply facility 800 a includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. The water supply facility 800a includes a first radiation measurement sensor 701 and a second radiation measurement sensor 702 similar to those of the seventh embodiment. Water supply facility 800 a further includes a return pipe 801 that branches from water supply pipe 130 and communicates with introduction pipe 110, and a switching valve 802 that is provided between water supply pipe 130 and return pipe 801. The control unit 40 controls the switching valve 802 based on the detection result. During normal operation, the switching valve 802 connects the upstream portion and the downstream portion of the water supply pipe 130 to block the flow path from the water supply pipe 130 to the return pipe 801.

  An example of state detection and control by the control unit 40 will be described below. For example, the control part 40 detects the 1st state which generate | occur | produced in the water supply equipment 800a, when the measured value of the 2nd radiation measurement sensor 702 exceeds a threshold value. The control unit 40 that has detected the first state shuts off the supply of water via the inlet pipe 110 by closing the inflow valve 112 and switches the switching valve 802 to return the upstream side portion of the water supply pipe 130 and the return, for example. The pipe 131 is connected to operate the pump 131. As a result, the water in the water receiving tank 120 is pressurized by the pump 131 installed in the water supply pipe 130, circulated to the introduction pipe 110 through the return pipe 801, and again passes through the radioactive substance adsorbing unit 140. A circulation path returning to the water tank 120 is formed.

  For example, when the radioactive substance concentration of water supplied from the water main 10 suddenly increases for some reason, the measured doses of the first radiation measurement sensor 701 and the second radiation measurement sensor 702 increase and exceed the threshold value. It is possible. In such a case, the inflow valve 112 is closed to temporarily shut off the supply of new water, and water is circulated through the return pipe 801 and repeatedly passed through the radioactive substance adsorbing unit 140, thereby supplying the water supply system. The radioactive material contained in the water can be removed to the same extent as usual.

  In addition, for example, when the radioactive substance adsorbing unit 140 has a reduced ability to adsorb radioactive substances due to damage to the radioactive substance adsorbing unit 140, the measurement value of the second radiation measurement sensor 702 may exceed the threshold value. Even in such a case, if the adsorption capacity of the radioactive substance adsorption unit 140 is not completely lost, the radioactive substance is removed to the same level as usual by circulating water through the return pipe 801. Can do.

Further, when the measurement value of the second radiation measurement sensor 702 falls below the threshold value, the control unit 40 switches the switching valve 802 again to connect the upstream side portion and the downstream side portion of the water supply pipe 130, and the water supply equipment 800a. The water supply to the water tap 20 may be resumed. The inflow valve 112 is opened again when the water supply is restarted or when the water level in the water receiving tank 120 is lowered after the restart. When the measured dose of the second radiation measurement sensor 702 again exceeds the threshold value, the control unit 40 controls to close the inflow valve 112 and switch the switching valve 802 to form a water circulation path via the return pipe 801. Try again. By repeating this, for example, until the radiation dose temporarily increased from the water supplied from the water main 10 is restored or the maintenance of the radioactive substance adsorption unit 140 is performed, the adsorption capability of the radioactive substance adsorption unit 140 is increased. The water supply can be continued intermittently until recovery.

  When water is circulated inside the water supply system as described above, the temperature of the water increases as the circulation is repeated. When the temperature of the water rises, not only the water supply equipment 800a is affected, but the life of the parts is shortened, and the water supplied to the faucet 20 becomes hot when resuming water supply, and in the worst case, the user may be burned. is there. Therefore, for example, a thermometer (not shown) is installed in an arbitrary position of the circulation path via the return pipe 801 or in the circulation path of the water supply pipe 130 such as the pump 131, and the control unit 40 is measured by the thermometer. The monitored temperature may be monitored. For example, if the temperature of the water exceeds the threshold before the measurement value of the radiation measurement sensor falls below the threshold, control is performed to avoid the influence on the water supply facility 800a due to the unexpectedly high temperature in the water supply system. The unit 40 may stop the pump 131. Alternatively, if the measured value of the second radiation measurement sensor 702 does not fall below the threshold value even after a predetermined time has elapsed since the start of the circulation operation, it is considered that the radioactive substance concentration cannot be lowered sufficiently in the circulation operation. The control unit 40 may stop the pump 131. In addition, even when the water supply stop and restart are repeated a predetermined number of times or more, it is considered that the root cause of the increase in the concentration of radioactive material has not been removed. The water faucet 20 may be shut off by forcibly stopping it.

  Drawing 8B is a figure showing roughly water supply equipment concerning the 1st modification of an 8th embodiment of the present invention. Referring to FIG. 8B, the water supply facility 800 b includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Further, the water supply facility 800b includes a first radiation measurement sensor 701, a second radiation measurement sensor 702, a return pipe 801, and a switching valve 802, similarly to the water supply facility 800a. A water supply facility 800b according to this modification is different from the water supply facility 800a described above in that it includes an additional radioactive substance adsorbing portion 803 provided in the return pipe 801. The additional radioactive substance adsorbing unit 803 may have the same configuration as the radioactive substance adsorbing unit 140, for example. However, since the additional radioactive substance adsorbing unit 803 is limitedly used in an abnormal state as described below, May not be as high as the radioactive substance adsorption unit 140.

  Even in the water supply facility 800b according to this modification, the control of the switching valve 802 by the control unit 40 can be the same as that of the water supply facility 800a. However, in this modification, since the radioactive substance adsorbing portion 803 is provided in the return pipe 801, the radioactive substance contained in the water passing through the return pipe 801 is adsorbed. Therefore, for example, the time taken to remove radioactive substances to the same extent as usual by circulating water via the return pipe 801 can be shorter than that of the water supply facility 800a. For example, when the radioactive substance adsorption | suction capability by the radioactive substance adsorption | suction part 140 is lost, even if it implements circulation operation in the water supply equipment 800a, a radioactive substance cannot be removed substantially. However, since the radioactive water adsorbing portion 803 is provided in the water supply facility 800b, the radioactive material can be removed to the same extent as usual by the circulation operation.

In addition, although the water supply equipment 800a which concerns on this embodiment as mentioned above was demonstrated as what provided the return piping 801 and the switching valve 802 in the water supply equipment 700b which concerns on 7th Embodiment, the water supply equipment 700c of a modification is provided. -700e may be similarly provided with a return pipe 801 and a switching valve 802. Further, similarly to the seventh embodiment, the configuration of the water supply facility as a base is not limited to the water supply facility 100 according to the first embodiment, and the second, third, and fourth embodiments. The water supply equipment 200, 300, 400 according to the above may be provided with a radiation measurement sensor, a control unit, a return pipe, and a switching valve.

  Furthermore, the water supply facility 800b according to the first modification of the present embodiment described above is provided with a return pipe 801, a switching valve 802, and a radioactive substance adsorbing portion 803 in the water supply facility 700b according to the seventh embodiment. However, similarly, the return pipe 801, the switching valve 802, and the radioactive substance adsorbing unit 803 may be provided in the water supply facilities 700c to 700e of the modified examples. Further, similarly to the seventh embodiment, the configuration of the water supply facility as a base is not limited to the water supply facility 100 according to the first embodiment, and the second, third, and fourth embodiments. The water supply equipment 200, 300, 400 according to the above may be provided with a radiation measurement sensor, a control unit, a return pipe, and a switching valve.

  FIG. 8C is a diagram schematically showing a water supply facility according to a second modification of the eighth embodiment of the present invention. Referring to FIG. 8C, the water supply facility 800 c includes an introduction pipe 510, a radioactive substance adsorption unit 520, a water supply pipe 530, and a control unit 40. In addition, the water supply facility 800c includes a first radiation measurement sensor 701 and a second radiation measurement sensor 702, similarly to the water supply facility 800a. The water supply facility 800c according to this modification is the same as that of the seventh embodiment, in which the radiation measurement sensor and the control unit are provided in the water supply facility 500 according to the fifth embodiment described above with reference to FIG. Similar to the variation. As a difference from the modified example of the seventh embodiment, a return pipe 804 and a switching valve 805 are provided in the present modified example. The return pipe 804 communicates from the water supply pipe 530 to the well 30 that is a water supply source. The switching valve 805 branches the return pipe 804 from the water supply pipe 530. The control unit 40 controls the switching valve 805 based on the detection result of the state. The switching valve 805 communicates the upstream portion and the downstream portion of the water supply pipe 530 in a normal state, and blocks the flow path to the return pipe 804.

  For example, when the radioactive substance concentration of water in the well 30 increases for some reason, the measurement values of the first radiation measurement sensor 701 and the second radiation measurement sensor 702 may exceed a threshold value. In such a case, the supply of water to the faucet 20 is temporarily interrupted by switching the switching valve 805, and the water that has once passed through the radioactive substance adsorbing unit 520 is returned to the well 30 via the return pipe 804. By this, the radioactive substance density | concentration of the water in the well 30 can be reduced and it can approximate to a normal value.

  In addition, for example, when the radioactive substance adsorption unit 520 is damaged or the radioactive substance adsorption capability of the radioactive substance adsorption unit 520 is reduced, the measurement value of the second radiation measurement sensor 702 may exceed the threshold value. . Even in such a case, unless the adsorption capacity of the radioactive substance adsorption unit 520 is completely lost, the radioactive substance concentration of the water in the well 30 is reduced by circulating water through the return pipe 804. be able to. If the radioactive substance concentration of the water in the well 30 is sufficiently reduced, the water from which the radioactive substance has been removed to the same level as normal is supplied to the faucet 20 even if the adsorption capacity of the radioactive substance adsorption unit 520 is reduced. Can be supplied.

  In the present modification as well, an additional radioactive substance adsorbing portion 803 can be provided in the return pipe 804 as in the water supply facility 800b according to the first modification described above. By providing the additional radioactive substance adsorbing portion 803, when the water is circulated through the return pipe 804, the radioactive substance concentration of the water in the well 30 can be reduced more quickly. In addition, when the radioactive substance adsorbing ability by the radioactive substance adsorbing part 520 is lost, the radioactive substance concentration in the water in the well 30 is reduced by the circulation operation only when the additional radioactive substance adsorbing part 803 is provided. be able to.

  In the water supply facilities 800a to 800c according to the eighth embodiment as described above, return pipes 801 and 804 are provided in addition to the configuration of the water supply facility according to the seventh embodiment. In the water supply facilities 800 a and 800 b where the water supply source is the water main pipe 10, the return pipe 801 is connected to the downstream side of the inlet valve 112 through the introduction pipe 110. In the water supply facility 800c, the return pipe 804 is connected to the well 30 that is a water supply source. Furthermore, in the water supply facilities 800a to 800c, switching valves 802 and 805 are provided at the inlets of the return pipes 801 and 803, respectively. The control unit 40 controls the switching valves 802 and 805 based on the state detection result.

  Moreover, although the dose of the second radiation measurement sensor 702 for detecting the first state is used, the first state is also set when the dose of the first radiation measurement sensor 701 exceeds an arbitrary threshold value. Circulation operation may be performed. In this case, the first radiation measurement sensor 701 measures the radiation dose accumulated in the radioactive substance adsorption unit 140, and the second radiation measurement sensor 702 measures the instantaneous radiation dose in the carrier liquid in the water supply pipe 130. The threshold value in the second radiation measurement sensor 701 may be larger than the threshold value in the first radiation measurement sensor 701. Furthermore, each threshold value may be an arbitrary dose or a change amount in a certain period.

  With the configuration as described above, in the present embodiment, the ability to remove radioactive substances contained in water can be improved by circulating water in the water supply system including the radioactive substance adsorbing units 140 and 520. Therefore, for example, the radioactive substance concentration of water supplied from the water supply source (the water main 10 or the well 30) is increased for some reason, or the adsorption capacity of the radioactive substance adsorption units 140 and 520 is lowered. For example, radioactive substances contained in water can be removed to the same extent as usual. Therefore, for example, the radioactive substance concentration of water supplied from the water supply source is lowered to the same level as usual, or the adsorption capacity is restored by replacing the radioactive substance adsorption cartridge or the radioactive substance adsorbent of the radioactive substance adsorption unit 140, 520. Until it is done, water supply can be continued intermittently. As a result, in the present embodiment, water supply can be continued within a minimum water cut-off range even in an unexpected situation that may occur regarding the removal of radioactive substances.

  Note that the modification of the present embodiment may be a modification of the sixth embodiment or the seventh embodiment. That is, in the water supply facility described above as the present embodiment or a modification thereof, in addition to the radiation measurement sensor, the control unit, the return pipe, and the switching valve, the radioactive substance adsorbing unit as described in the sixth embodiment A pressurizing pump 601 that pressurizes 140 may be provided. Or the output part like the water supply equipment 700a which concerns on the modification of 7th Embodiment, the communication part like the water supply equipment 700d, or the 3rd radiation measurement sensor like the water supply equipment 700e may be provided.

(Ninth embodiment)
FIG. 9 is a diagram schematically showing a water supply facility according to the ninth embodiment of the present invention. Referring to FIG. 9, the water supply facility 900 includes an introduction pipe 110, a water receiving tank 120, a water supply pipe 130, a radioactive substance adsorption unit 140, and a control unit 40. Since these components are the same as those in the first embodiment, a detailed description thereof is omitted. Further, the water supply facility 900 includes a pressure sensor 901 control unit 40 provided in the water supply pipe 130 on the downstream side of the pump 131. The control unit 40 includes an output unit (described later) such as a display unit. In addition, the control unit 40 may include a communication unit that transmits a notification similar to the notification output from the output unit to the remote monitoring device or an external display, together with or instead of the output unit. A specific configuration example of the control unit 40 will be described later.

In the illustrated example, the control unit 40 acquires the pressure value measured by the pressure sensor 901 and calculates the rotation speed of the pump 131. More specifically, as described in the first embodiment, the control unit 40 controls the inverter 133 to change the rotation speed of the pump 131 to perform the discharge pressure constant control or the estimated terminal pressure constant control. . In other embodiments, the inverter 133 is not provided, the pump is rotated at a fixed speed, the discharge pressure is made constant by a pressure reducing valve (not shown), or the control unit 40 causes the plurality of pumps 131 to be disconnected in parallel. Adjustment of the pressure may be realized. And the control part 40 determines the maintenance time of the radioactive substance adsorption | suction part 140 based on the calculated rotation speed of the pump 131, and the measured pressure. Note that the rotational speed of the pump 131 may be an actual value obtained by providing a rotational speed sensor (not shown) in the pump 131 or the motor 132 without using the value calculated by the control unit 40.

  Here, the maintenance of the radioactive substance adsorbing unit 140 includes, for example, replacement of the radioactive substance adsorbing cartridge or the radioactive substance adsorbing material included in the radioactive substance adsorbing unit 140. As described above with reference to the seventh embodiment, the radioactive substance adsorption unit 140 accumulates the adsorbed radioactive substance. If the radioactive substance adsorption unit 140 is continuously used without exchanging the radioactive substance adsorption cartridge or the radioactive substance adsorbent, the amount of radiation from the accumulated radioactive substance becomes too high, and the radioactive substance adsorption cartridge or the radioactive substance adsorption thereafter. There is a possibility of hindering the work of replacing materials. Therefore, it is beneficial to output a notification of maintenance of the radioactive substance adsorbing unit 140 at an appropriate time and to promote replacement of the radioactive substance adsorbing cartridge or the radioactive substance adsorbing material.

  In many cases except for a sudden case such as a nuclear accident, the concentration of radioactive material in the water supplied from the water main 10 can be regarded as almost constant. Therefore, for example, the amount of radioactive material adsorbed by the radioactive material adsorption unit 140 and accumulated therein can be estimated from the accumulated flow rate in the water supply facility 900. More specifically, for example, the accumulated amount of radioactive material can be regarded as a function of the accumulated flow rate. Therefore, in this embodiment, the control part 40 performs determination of the maintenance time of the radioactive substance adsorption | suction part 140 using a cumulative flow rate as a usage-amount index of water supply equipment.

  More specifically, the control unit 40 determines the maintenance time of the radioactive substance adsorbing unit 140 based on the rotation speed of the pump 131 and the pressure measured by the pressure sensor 901. In this example, the means for obtaining the usage amount index of the water supply facility 900 includes a pressure sensor 901. The pumping water flow rate of the pump 131 can be calculated from the rotation speed of the pump 131 and the measured pressure value. Since all the water supplied by the water supply facility 900 is pumped by the pump 131, the cumulative flow rate of the water supply facility 900 can be calculated by integrating the calculated pumping flow rate. The control unit 40 can determine whether or not the maintenance time of the radioactive substance adsorbing unit 140 has come, for example, by comparing the calculated accumulated flow rate with a threshold value.

  Note that the cumulative flow rate of the water supply facility 900 does not necessarily have to be calculated based on the pumped water flow rate of the pump 131. For example, a flow meter may be provided in the introduction pipe or the water supply pipe, and the flow rate measured by the flow meter may be integrated. In this case, the means for obtaining the usage index of the water supply facility 900 includes a flow meter.

The output unit outputs a notification directed to the administrator or operator of the water supply facility 900 based on the determination result. Furthermore, the control unit 40 may control the inflow valve 112 or the pump 131 based on the determination result. For example, when the control unit 40 determines that the maintenance time of the radioactive substance adsorbing unit 140 has arrived, the output unit outputs information indicating that the maintenance time has arrived, more specifically, a notification that prompts maintenance. . In addition, for example, in order to prevent further accumulation of radioactive material in the radioactive substance adsorption unit 140 when the maintenance of the radioactive substance adsorption unit 140 is not performed even after the output of the notification by the output unit, the control unit 40
The inflow valve 112 or the pump 131 is controlled so that the supply of water to the water tap 20 is stopped. More specifically, the controller 40 stops the supply of water by closing the inflow valve 112 or stopping the pump 131.

  In the above example, the control unit 40 compares the calculated cumulative flow rate with the first threshold value, and determines that the maintenance time of the radioactive substance adsorbing unit 140 has arrived when the cumulative flow rate exceeds the first threshold value. . At this point, the output unit outputs a notification for the administrator operator. Thereafter, when the accumulated flow rate increases without going through the resetting of the usage index as described below and exceeds a second threshold value that is larger than the first threshold value, or a predetermined time without resetting. When it has elapsed, the control unit 40 determines that the maintenance is not performed, and controls the inflow valve 112 or the pump 131 so that the supply of water is stopped.

  On the other hand, in the above example, when maintenance of the radioactive substance adsorbing unit 140 is performed, the accumulated flow rate held by the control unit 40, that is, the usage amount index of the water supply facility 900 is reset. The reset may be executed by, for example, an operation input of an administrator or an operator via an input device including a button, a lever, a keyboard, a mouse, or a touch panel included in or connected to the control unit 40. . Alternatively, the reset may be automatically performed via a switch or a sensor (not shown) arranged to operate when the radioactive substance adsorbing cartridge of the radioactive substance adsorbing unit 140 or the radioactive substance adsorbing material is replaced, for example. . By such reset, the control unit 40 can appropriately determine the next maintenance time of the radioactive substance adsorbing unit 140.

  As a modification of the present embodiment, the control unit 40 may use the accumulated operation time as a usage index for the water supply facility 900. When the concentration of radioactive material in the supplied water can be regarded as almost constant, and when the flow rate per hour during operation of the water supply equipment 900 can be regarded as almost constant, it is adsorbed by the radioactive material adsorption unit 140 and accumulated therein. The amount of radioactive material present can be estimated from the cumulative operating time of the water supply equipment. More specifically, for example, the accumulated amount of radioactive material can be regarded as a function of the cumulative operation time. Therefore, in the present modification, the control unit 40 determines the maintenance time of the radioactive substance adsorbing unit 140 by using the cumulative operation time as the usage amount index of the water supply facility.

  More specifically, for example, the control unit 40 increments the cumulative operation time of the water supply facility 900 while the pump 131 is activated. In this example, the control unit 40 is considered to be continuously activated during operation of the water supply facility 900. Moreover, in this example, the means for acquiring the usage amount index of the water supply facility 900 includes the control unit 40 itself. When the maintenance of the radioactive substance adsorbing unit 140 is performed, the control unit 40 determines whether or not the maintenance period of the radioactive substance adsorbing unit 140 has arrived, for example, by comparing the cumulative operation time with a threshold. Reset the accumulated accumulated operation time. In addition, the process after determination is the same as that of the example using said cumulative flow rate.

  In the above, an example in which the flow rate per hour during operation of the water supply facility 900 can be regarded as almost constant has been described. However, the amount of water supplied is extremely small, and the adsorption capacity of the radioactive substance adsorption unit 140 is extremely high. If it is expected to be several years to several tens of years or hundreds of years before the maintenance period of the radioactive material adsorbing unit 140, the flow rate of the pump 131 is assumed to be the maximum flow rate, and a threshold value to be compared with the accumulated operation time is determined. May be. Furthermore, it is good also as a threshold value with a certain amount of margin. In this case, the time when the maintenance time of the radioactive substance adsorbing unit 140 arrives is earlier, can be replaced more safely, and even if there is a moment when the radiation dose of the supply liquid suddenly increases before reaching the threshold, There is a high possibility that the radioactive substance adsorbing unit 140 will have a radiation dose that does not hinder the work during maintenance.

  As a further modification, the control unit 40 may increment the cumulative operation time according to a signal received from a device other than the control unit 40 when using the cumulative operation time as a usage index of the water supply facility 900. The device that transmits the signal is a device that can be regarded as being continuously activated during the operation of the water supply facility 900, similarly to the control unit 40. In this case, the means for obtaining the usage index of the water supply facility 900 includes a device that transmits a signal.

  Alternatively, the control unit 40 may increment the cumulative operation time while the power supply to the device included in the water supply facility 900 is continued. The power supply to the apparatus can be detected using, for example, a galvanometer provided in the electrical wiring. The device from which power feeding is detected is a device that can be regarded as being continuously activated during the operation of the water supply facility 900, such as the water level gauge 122, as in the control unit 40 described above. However, unlike the control unit 40, this device may not have a function of transmitting a signal. In this case, the means for obtaining the usage index of the water supply facility 900 includes a galvanometer.

  The controller 40 may use the energization time instead of the cumulative operation time of the pump 131. Since the pump 131 is started and stopped by a command from the control unit 40, it is impossible to supply water unless the control unit 40 is energized. The control unit 40 always counts the energization time while its own power is turned on, and periodically stores it in a non-volatile memory (not shown). The time when the energization time becomes equal to or greater than the above threshold is defined as the maintenance time. By using the energization time instead of the accumulated operation time of the pump 131, the maintenance work can be performed more safely.

  Note that, as in the above-described modification, when the cumulative operation time is used as the usage amount index of the water supply facility 900, the cumulative flow rate may not be used as the usage amount index. In this case, the pressure sensor 901 is not provided or is not used for acquiring a usage amount index. Alternatively, both the accumulated flow rate and the accumulated operation time may be used as a usage index of the water supply facility 900. In this case, for example, threshold determination may be performed for each usage index, and determination regarding the maintenance time of the radioactive substance adsorbing unit 140 may be executed using a logical product or logical sum of the determination results.

  In the present embodiment, by using the usage amount index of the water supply facility 900, it is possible to appropriately execute the determination regarding the maintenance time of the radioactive substance adsorbing unit 140. The usage amount index of the water supply facility 900 does not necessarily directly indicate the cause that the maintenance of the radioactive substance adsorbing unit 140 is required, for example, the accumulated quantity of radioactive substance. However, when such an amount can be estimated from the usage index of the water supply equipment 900 as described above, the maintenance timing of the radioactive substance adsorbing unit 140 is determined more easily than when, for example, a radiation measurement sensor is used. There is a possibility.

  In addition, although the water supply equipment 900 which concerns on this embodiment was demonstrated as what provided the pressure sensor 901 and the control part 40 in the water supply equipment 100 which concerns on 1st Embodiment, the effect of these components is a water receiving tank. The other configurations of the water supply facility provided with, for example, the second and third embodiments can be similarly obtained. That is, as a modification of the present embodiment, in the water supply facility 200 shown in FIG. 2, for example, a pressure sensor is provided in the water supply pipe 130 and a control unit that performs determination using the detection result of the pressure sensor is provided. Also good. Similarly, for example, in the water supply facilities 300a and 300b shown in FIGS. 3A and 3B, for example, a pressure sensor is provided in the water supply pipe 130, and a control unit that performs determination using the detection result of the pressure sensor is provided. Also good.

Furthermore, the modification of this embodiment can also include a directly-connected water supply system in which a water receiving tank is not provided. That is, even when the radioactive substance adsorbing unit is provided in the directly connected water supply system, it may be possible to adopt the same configuration as the radiation measurement sensor and the control unit 40 in the present embodiment. More specifically, for example, in the water supply facilities 400a and 400b according to the fourth embodiment described above with reference to FIGS. 4A and 4B, for example, pressure sensors are provided in the water supply pipes 430a and 430b, and pressure is further increased. You may provide the control part which performs determination using the detection result of a sensor. Similarly, in the water supply facility 500 according to the fifth embodiment described above with reference to FIG. 5, for example, a pressure sensor is provided in the water supply pipe 530 and the determination is performed using the detection result of the pressure sensor. A control unit may be provided.

  The modification of the present embodiment can also be a modification of the sixth embodiment, the seventh embodiment, or the eighth embodiment. That is, in the water supply facility described above as the present embodiment or the modification thereof, a pressurizing pump as described in the sixth embodiment may be provided in addition to the radiation measurement sensor and the control unit.

  Here, a modification of the seventh embodiment will be described as a modification of the present embodiment. As a modification of the present embodiment, a second radiation measurement sensor 702 may be provided on the secondary side of the pump 131 as in the modifications 700b to 700e. Since the calculation of the maintenance time in the water supply facility 900 according to the present embodiment is an estimated value, an unexpected sudden and sudden increase in dose cannot be estimated. Therefore, by additionally providing the radiation measurement sensor 702, it is possible to measure the actual value of the dose of water supplied to the faucet 20, and to stop the water supply when the dose increases. Here, the first radiation measurement sensor 701 described in the seventh embodiment may not be used in combination. Instead of providing the first radiation measurement sensor 701, the determination of the maintenance time described in the water supply facility 900 of this embodiment is advantageous in terms of cost. Further, a third radiation measurement sensor 708 may be provided. As described above, the radiation measurement sensors 701, 702, and 708 described in the seventh embodiment are provided in combination, and the water supply is controlled based on the combination with the detection result, and the same notification means as in the seventh embodiment. The notification of the maintenance time may be output at. Furthermore, the return pipe 801 and the switching valve 802 and / or the radioactive substance adsorbing unit 803 as described in the eighth embodiment may be provided, and the circulation flow path may be formed based on the detection result of the state. .

(Tenth embodiment)
FIG. 10 is a diagram schematically showing a water supply facility according to the tenth embodiment of the present invention. Referring to FIG. 10, water supply facility 1000 includes a first introduction pipe 1110 and a second introduction pipe 1210 that are respectively connected to water main pipe 10 that is a water supply source. The water supply facility 1000 includes a first water receiving tank 1120 that stores water supplied from the introduction pipe 1110 and a second water receiving tank 1220 that stores water supplied from the second introduction pipe 1210. Water supply facility 1000 includes a connecting pipe 1021 that connects first water receiving tank 1120 and second water receiving tank 1220 to each other. The connecting pipe 1021 is provided with a gate valve 1022. The water supply facility 1000 includes a water supply pipe 1030 that supplies water stored in the first water receiving tank 1120 or the second water receiving tank 1220 to the water tap 20 that is a water demand destination.

  Further, the water supply facility 1000 is connected to the first radioactive substance adsorbing portion 1140 connected to the introduction pipe 1110 inside the first water receiving tank 1120 and to the second introduction pipe 1210 inside the second water receiving tank 1220. And a second radioactive substance adsorbing unit 1240. In this embodiment, the 1st and 2nd radioactive substance adsorption | suction parts 1140 and 1240 are arrange | positioned so that it may not be immersed in the water stored by the 1st and 2nd water receiving tanks 1120 and 1220, respectively.

The first and second introduction pipes 1110 and 1210 are provided with check valves 1111 and 1211 and inflow valves 1112 and 1212, respectively. The check valves 1111 and 1211 prevent water that has entered the introduction pipe 1110 or the second introduction pipe 1210 from flowing back to the water main pipe 10. The inflow valves 1112 and 1212 are opened and closed by the control unit 40. More specifically, the inflow valves 1112 and 1212 are opened and closed according to the water levels in the first and second water receiving tanks 1120 and 1220, respectively. In the present embodiment, the control unit 40 controls the gate valve 1022 in addition to the inflow valves 1112 and 1212. A specific configuration example of the control unit 40 will be described later.

  The first and second water receiving tanks 1120 and 1220 are respectively provided with water level gauges 1122 and 1222 similar to the water level gauge 122 in the first embodiment. The water level meter 1122 can detect the water level of the first water receiving tank 1120, and the water level meter 1222 can detect the water level of the second water receiving tank 1220, respectively. When the gate valve 1022 is opened, the first and second water receiving tanks 1120 and 1220 communicate with each other. Therefore, the detection result of one of the water level gauges 1122 and 1222 is the first and second water receiving tanks. The water level common to 1120 and 1220 may be treated. Further, the water level detected by the water level gauges 1122 and 1222 may be used for controlling the pump 131 provided in the water supply pipe 1030 as described later. In addition, in order to avoid that drawing becomes complicated, illustration is abbreviate | omitted about the communication path | route from the water level meters 1122 and 1222 to the control part 40. FIG. Moreover, the 1st and 2nd water receiving tanks 1120 and 1220 may be provided with an overflow pipe (not shown) similar to the overflow pipe 121 in the first embodiment, as necessary.

  The water supply pipe 1030 is provided with a pump 131. The pump 131 is driven by the motor 132 and the inverter 133 and supplies water to the water tap 20. In the illustrated example, the pump 131 is also controlled by the control unit 40 in the same manner as the inflow valves 1112 and 1212. The control of the pump 131 by the control unit 40 can be the same as the control of the pump 131 by the control unit 40 in the first embodiment, for example.

  The first and second radioactive substance adsorption units 1140 and 1240 include, for example, a radioactive substance adsorption cartridge, similarly to the radioactive substance adsorption unit 140 in the first embodiment. The radioactive substance adsorbing cartridge is configured to be filled with a granular radioactive substance adsorbing material inside the housing. A water flow path is formed inside the housing so that water supplied from the introduction pipes 110 and 1210 efficiently passes through the radioactive substance adsorbent. Such a configuration filled with the granular radioactive material adsorbent can increase the adsorbent weight per volume, and is suitable for treating a large amount of water. However, instead of or in addition to the granular radioactive substance adsorbent, a cloth or activated carbon carrying the radioactive substance adsorbent may be used. In this case, since the reaction rate of the radioactive substance adsorbent is excellent, it is suitable for removing a low concentration radioactive substance. And when activated carbon is used, advantageous chlorine, odor, trihalomethane and the like can be removed from the water together with radioactive substances.

  Examples of radioactive material adsorbents include ion exchange resin, ion exchange fiber, chelate resin, chelate fiber, calcium alginate, chitosan, iron oxide, activated carbon, silver zeolite, silver phosphate, hydrotalcite, geopolymer, titanium oxide, silica gel, Preferably, at least one of amorphous aluminum silicate, zeolite, titanate, silicotitanate, manganese oxide, ferrocyanide, hydroxyapatite, cerium hydroxide, and zirconium hydroxide is included.

For example, radioactive cesium is effectively adsorbed by using ion exchange resin, ion exchange fiber, zeolite, ferrocyanide, titanate, amorphous aluminum silicate, silicotitanate, etc. as a radioactive material adsorbent. be able to. Further, for example, as a radioactive material adsorbent, ion exchange resin, ion exchange fiber, chelate resin, chelate fiber, calcium alginate, chitosan, zeolite, titanate, amorphous aluminum silicate, silicotitanate, hydroxyapatite, geo By using a polymer or the like, radioactive strontium can be effectively adsorbed. Furthermore, radioactive iodine can be adsorbed by using iron oxide, activated carbon, silver zeolite, silver phosphate, hydrotalcite, titanium oxide, silica gel, manganese oxide, cerium hydroxide or the like as the radioactive material adsorbent.

  As the radioactive material adsorbent, one type of adsorbent may be used, or a plurality of types of adsorbent may be used. For example, adsorbents that adsorb different radioactive substances may be mixed and used, or a plurality of types of adsorbents that adsorb a single radioactive substance may be mixed and used.

  Furthermore, for example, when titanate, amorphous aluminum silicate, silicotitanate or the like is used, radioactive cesium and radioactive strontium can be effectively removed simultaneously with a single adsorbent.

  It is known that the adsorption performance of ion exchange resins and zeolites that are cesium adsorbents decreases under conditions where the salt concentration is high. Similarly, iodine adsorbents are known to have poor adsorption performance under conditions of high salinity due to the similar chemical properties of iodine and chlorine. Further, the adsorption performance of the strontium adsorbent is also affected by the concentration of calcium or magnesium, and the adsorption performance is lowered under these high concentration conditions.

  Therefore, when contaminated water having a high concentration of salinity, calcium, or magnesium is to be treated, it is preferable to use an adsorbent with a small decrease in adsorption performance. Examples of such adsorbents include ferrocyanide and silicotitanate as radioactive cesium adsorbents. Examples of the radioactive strontium adsorbent include titanate and silicotitanate. Furthermore, examples of the radioactive iodine adsorbent include silver zeolite, silver phosphate, titanium oxide, manganese oxide, and cerium hydroxide.

  Among the radioactive material adsorbents, some adsorbents can remove heavy metals such as Pb, Cd, Hg, Zn, Cu, Ni, and Cr that are to be removed by the general water treatment. Further, Sb, As, Se, B, P, Si, white metal, etc., which are often in the form of oxo acid, can be removed.

  In the water supply facility 1000 that supplies drinking water, it is preferable to use a material that does not contain aluminum and aluminum compounds as the radioactive material adsorbent. In this way, it is possible to prevent aluminum that is suspected to be a cause of Alzheimer's disease from being contained in water.

  In the illustrated example, the first and second radioactive substance adsorbing units 1140 and 1240 are arranged so as not to be immersed in the water stored in the first and second water receiving tanks 1120 and 1220, respectively. The first and second radioactive substance adsorbing portions 1140 and 1240 are provided with radiation shielding structures 1141 and 1241, respectively.

  An example of control of the inflow valves 1112 and 1212 and the gate valve 1022 executed by the control unit 40 in the present embodiment will be described below. First, at the time of normal water supply, that is, when both the first and second water receiving tanks 1120 and 1220 and the first and second radioactive substance adsorbing units 1140 and 1240 are in a usable state, the control unit 40 includes a gate valve. Open 1022. As a result, the first and second water receiving tanks 1120 and 1220 communicate with each other, and the two water receiving tanks can be handled integrally. Therefore, the control unit 40 determines the control of the inflow valve 1112 and the pump 131 operation stop due to the drought state based on the detection result of the water level gauge 1122 provided in the first water receiving tank 1120. Alternatively, the control unit 40 determines the first based on the detection result of the water level gauge 1222 provided in the second water receiving tank 1220 (same as the detection result of the water level gauge 1122 provided in the first water receiving tank 1120). The control of the inflow valve 1212 provided in the second introduction pipe 1210 and the pump 131 operation stoppage due to the drought state may be determined.

  Here, the pressure of the water main 10 varies depending on the region. However, since the water supply equipment 1000 is installed in a fixed place, it is generally constant to some extent or periodically fluctuates in a 24-hour cycle. Therefore, it is possible to estimate the amount of water that has flowed to the first and second radioactive substance adsorbing units 1140 and 1240 by measuring the period during which the inflow valves 1112 and 1212 are open. Therefore, the maintenance time of the radioactive substance adsorbing unit 1140 and the radioactive substance adsorbing unit 1240 can be estimated.

  Further, in normal times (when the first water receiving tank 1120 and the second water receiving tank 1220 can be shared), the control unit 40 opens the gate valve 1022 and the control unit 40 sets the water level meter of the first water receiving tank. The signal 1122 is enabled and only the first inflow valve 1111 is controlled to supply water using only the supply pipe 1110. This means that water is passed only through the first radioactive substance adsorbing unit 1140, and there is a difference between the maintenance period of the first radioactive substance adsorbing part 1140 and the maintenance period of the second radioactive substance adsorbing unit 1240. means. Thereby, during the maintenance of the first radioactive substance adsorbing part 1140, the second radioactive substance adsorbing part 1240 can continue to supply water, and the water cut off at the faucet 20 can be avoided.

  When the first radioactive substance adsorption unit 1140 determines that the maintenance is necessary, the control unit 40 closes the inflow valve 1112 provided in the introduction pipe 1110 and forcibly closes the gate valve 1022. Furthermore, water supply to the water tap 20 is continued by selecting the second water receiving tank and controlling the inflow valve 1212 provided in the second introduction pipe 1210. As a result, water does not pass through the first radioactive substance adsorbing part 1140 and maintenance becomes possible. In addition, the second introduction pipe 1210 and the second radioactive substance adsorbing part 1240 provide a water receiving tank 1220. Water level can be secured, and water supply to the water tap 20 is continued. Even when the second radioactive substance adsorption unit 1240 determines that the maintenance is necessary, the control unit 40 closes the inflow valve 1212 provided in the introduction pipe 1210 and forces the gate valve 1022. The water supply is continued in the first water receiving tank.

  Since radiation is invisible but has a great influence on the human body, it is necessary to perform maintenance of the radioactive substance adsorption units 1140 and 1240 without fail, and use of the radioactive substance adsorption units 1140 and 1240 before the adsorption performance deteriorates. It is important to stop. Also, since water supply is a lifeline, water outage should be avoided as much as possible.

  The gate valve is also used when cleaning the water receiving tanks 1120 and 1220. The cleaning staff performs cleaning after selecting either the first water receiving tank 1120 or the second water receiving tank 1220 which continues water supply. Therefore, not only the opening / closing control from the control unit 40 but also a mechanism in which the cleaning staff can manually open and close is possible. Moreover, the control part 40 is provided with the display part which a cleaning person can recognize which water receiving tank is selected among the water receiving tanks 1120,1220.

  In addition, although the water supply equipment 1000 which concerns on this embodiment was demonstrated as what doubled the introduction pipe, the water receiving tank, and the radioactive substance adsorption | suction part in the water supply equipment 100 which concerns on 1st Embodiment, the effect of duplication is In other configurations of the water supply equipment provided with the water receiving tank, for example, in the second and third embodiments, the water receiving tank is duplicated and controlled in the same manner as in this embodiment. That is, as a modification of the present embodiment, in the water supply facility 200 according to the second embodiment, the introduction pipe, the water receiving tank, and the radioactive substance adsorbing unit may each be doubled.

  Similarly, in the water supply facilities 300a and 300b shown in FIGS. 3A and 3B, the introduction pipe, the water receiving tank, and the radioactive substance adsorbing unit may be doubled. In this case, it is not necessary to drain the water stored in the water receiving tank during maintenance, but the inflow valve is closed. Therefore, the configuration of the present embodiment in which water supply can be continued using the other inflow valve even when one inflow valve is closed can be advantageous.

  The modification of the present embodiment may be a modification of the sixth embodiment, the seventh embodiment, the eighth embodiment, or the ninth embodiment. For example, in the water supply facility described above as the present embodiment or the modification thereof, a pressurizing pump as described in the sixth embodiment may be provided. For example, in the example shown in FIG. 10, a pressure pump is provided upstream of the first and second radioactive substance adsorbing units 1140 and 1240, respectively.

  In addition, for example, in the water supply facility described above as the present embodiment or the modification thereof, the radiation measurement sensor and the control unit as described in the seventh embodiment are provided, and the water supply is performed based on the detection result of the state. Control or notification output may be implemented. For example, in the example shown in FIG. 10, radiation measurement sensors are provided in the first and second radioactive substance adsorption units 1140 and 1240 and the third water supply pipe 1030.

  In addition, for example, in the water supply facility described above as the present embodiment or a modification thereof, the return pipe and the switching valve as described in the eighth embodiment are provided, and the circulation flow is based on the detection result of the state. A path may be formed. For example, in the example shown in FIG. 10, the return pipe communicates from the third water supply pipe 1030 to the introduction pipe 1110 and the second introduction pipe 1210. In this case, since a branch portion is generated in the return pipe, a switching valve is also provided in this branch portion, and the return pipe communicates with the side of the water supply pipe that leads to a usable (for example, not under maintenance) radioactive substance adsorbing section. Thus, the control unit 40 may control this switching valve.

  In addition, for example, in the water supply facility described above as the present embodiment or a modification thereof, an acquisition unit and a control unit as described in the ninth embodiment are provided, and the first and the first based on the calculation result are provided. The determination regarding the maintenance time of 2 radioactive substance adsorption | suction parts 1140 and 1240 may be performed. For example, in the example shown in FIG. 10, a pressure sensor is provided downstream of the pump 131 of the third water supply pipe 1030, and the pressure detected by the pressure sensor and the rotation speed of the pump 131 set by the control unit 40 are used. The maintenance time of the first and second radioactive substance adsorbing units 1140 and 1240 may be determined based on the accumulated flow rate calculated based on the accumulated flow rate. As in the above example, since one of the first and second radioactive substance adsorbing units 1140 and 1240 can be used at the same time, the control unit 40 can open / close the inflow valves 1112 and 1212, for example. The cumulative flow rate may be calculated individually for each of the introduction pipe 1110 and the water supply pipe 1210.

(Configuration example 1 of control unit)
Next, with reference to FIG. 11, a control unit 40-1 that is a first configuration example of the control unit 40 in each embodiment described above will be described.

  As illustrated in FIG. 11, the control unit 40-1 includes a storage unit 47, a calculation unit 48, an I / O unit 50, a setting unit 46, and a display unit 49. The setting unit 46 and the display unit 49 are provided in the operation panel 51 of the water supply facility.

  The setting unit 46 is used to set various setting values necessary for water supply by an external operation. Various setting values set in the setting unit 46 are stored in the storage unit 47. As an example, the user can input stop pressure, starting pressure, and other information necessary for control via the setting unit 46.

  The display unit 49 functions as a user interface, and various data such as set values stored in the storage unit 47, the current operation state (operation state) of the pump, for example, operation or stop of the pump, operation frequency, current, Displays suction side pressure, discharge side pressure, necessity of parts replacement, water tank alarm, etc.

  As the storage unit 47, a memory such as a RAM or a ROM is used. The storage unit 47 stores various data, for example, calculation result data (operation time, integrated value, etc.) in the calculation unit 48, pressure values (suction side pressure, discharge side pressure), data input through the setting unit 46, and I Data or the like input through the / O unit 50 or output through the I / O unit 50 is stored.

  A port or the like is used as the I / O unit 50. The I / O unit 50 receives a signal such as an output value of the pressure sensor and sends it to the calculation unit 48. In each of the above embodiments, the inverter is provided with a rotation speed sensor (not shown) that detects the rotation speed of the motor. The I / O unit 50 receives the detection value (the number of rotations of the motor) of the rotation number sensor via the inverter and sends it to the calculation unit 48. However, the rotation speed sensor is not limited to that provided in the inverter. Further, when using an inverter that controls the rotational speed without the rotational speed sensor, the rotational speed sensor does not exist and is assumed to be virtual. The I / O unit 50 also performs input / output of signals in communication.

  A CPU is used as the calculation unit 48. The calculation unit 48 sets, measures, and calculates various data for operating the pump based on programs and various data stored in the storage unit 47 and signals input from the I / O unit 50. Do. An output from the calculation unit 48 is input to the I / O unit 50.

  Further, the I / O unit 50 and the inverter are connected to each other by communication means such as RS422, 232C, and 485. Control signals such as various set values, frequency command values, start / stop signals (operation / stop signals) are sent from the I / O unit 50 to the inverter, and the actual frequency values and the like are transmitted from the inverter to the I / O unit 50. The operation status (operating state) such as current value is sent sequentially.

  An analog signal and / or a digital signal can be used as a control signal transmitted and received between the I / O unit 50 and the inverter. For example, an analog signal can be used for the rotation frequency or the like, and a digital signal can be used for the operation stop command or the like.

  A water level gauge, an inverter, and a pressure sensor are connected to the control unit 40-1 via a signal line.

(Configuration example 2 of control unit)
Next, a control unit 40-2 that is a second configuration example of the control unit 40 in each embodiment described above will be described with reference to FIG.

  In the example shown in FIG. 12, in addition to the display unit 49 of the control unit 40-1, an external display 81 is further provided. The external indicator 81 may be configured as a part of the water supply device or may be configured as an external device. The external display 81 may be a display that can display information that is equivalent to or more detailed than the operation panel 51 described above, or that can perform complicated operations.

The control unit 40-2 further includes a communication unit 80, and is connected to the external display device 81 by wired communication or wireless communication. Further, in the control unit 40-2, the operation panel 51 is provided with a reset button 52 and a clear button 53. By pressing the clear button 53, only the displayed message such as “the measured value of the radiation measurement sensor has exceeded the threshold” or “cartridge maintenance is required” is deleted. Further, when the reset button 52 is pressed, the control unit 40-2 may clear, for example, the integrated value of the electric energy to 0, and cancel the display of the cartridge replacement time and the pump stop state. Since the water supply equipment is a lifeline, there is a case where it is desired to continue water supply even if the radioactive substance adsorbing portion does not function normally. For example, until the maintenance staff rushes, the user can press the reset button 52 so that the water supply can be continued even in a situation where the cartridge is not replaced.

  As the external display 81, for example, a general-purpose terminal device such as a smartphone, a mobile phone, a personal computer, a tablet, or a dedicated terminal device such as a remote monitor is adopted. As the display unit 49, a simple indicator such as a 7-segment LED and an indicator lamp can be adopted. Further, as the external display 81, a high-function display on a liquid crystal screen using a touch input method or a push button method can be adopted. In this case, simple information can be displayed on the display unit 49, and a large amount of information can be displayed on the external display 81. With this configuration, the external display 81 displays, for example, the state of the water supply equipment such as “the measured value of the radiation measurement sensor has exceeded the threshold value” or “the maintenance of the cartridge (of the radioactive material adsorption unit) is necessary”. By doing so, even a user unfamiliar with the water supply facility can recognize the state of the water supply facility without misunderstanding. Moreover, a water supply apparatus may be installed in an environment with much electrical noise, such as a machine room or a pump room. In preparation for such a case, as the display unit 49, a display unit including a 7-segment LED, a display lamp, a mechanical press button, etc., which are more resistant to electrical noise than a liquid crystal display or a touch panel may be used. Thus, even when an abnormality occurs in the liquid crystal display or touch panel operation of the external display 81 due to electrical noise generated from the external environment, the display unit 49 displays the minimum display and operation necessary for the operation of the water supply device. It can be carried out. Therefore, the water supply device can be installed even in an environment with a lot of electrical noise.

  Furthermore, when a general-purpose terminal device such as a smartphone, a mobile phone, a personal computer, or a tablet is adopted as the external display 81, dedicated application software for acting as the external display 81 is applied to these devices. It may be installed. In this case, it is possible to provide a display operation in accordance with the level or purpose of the user by preparing and using a plurality of dedicated application software.

  Here, the operation panel 51 (display unit 49) is not provided in the control unit 40-2, and only the external display (high function display) 81 may be provided instead. In this case, all the functions of the operation panel described above can be implemented by the external display 81. Since it is not necessary to provide the display device itself in the water supply apparatus, it is possible to further reduce the cost of the entire water supply apparatus. Further, the reset button 52 and the clear button 53 may not be provided in the setting unit 46 of the operation panel 51, and instead, the reset button (not shown) or the clear button (not shown) may be provided in the external display 81. When the clear button on the external display 81 is pressed, the display displayed on the external display 81 is deleted.

  In FIG. 12, the communication unit 80 is connected to a remote monitoring device (for example, a personal computer, a smartphone, or a dedicated monitor) provided in a maintenance management company or an administrator room via a public line, a network, a dedicated line, or the like. You may communicate. In this case, for example, information related to pump control in the water supply apparatus is transmitted from the communication unit 80 to the remote monitoring apparatus. The remote monitoring device includes water supply pump operation information (water supply pressure, pump speed, etc.), maintenance information (operation time, number of starts, consumable parts usage period, failure history, etc.), equipment information (product number, parts replacement history, etc.) Other information such as a parts list) may also be displayed.

FIG. 13 is a diagram showing a modification of the control unit and the external display shown in FIG. The control unit 40-3 shown in FIG. 13 includes a control unit side antenna unit 67 instead of the communication unit 80, and an integrated circuit 68 connected to the control unit side antenna unit 67. Thus, it is different from the control unit 40-2. The integrated circuit 68 is electrically connected to a storage unit 47 having a nonvolatile value storage area and a volatile storage area. Note that the control unit 40-3 illustrated in FIG. 13 does not include the display unit 49, but may include the display unit 49. Moreover, the external indicator 70 shown by FIG. 13 may be comprised as a part of water supply apparatus, and may be comprised as an external device.

  The external display device 70 includes a display-side antenna unit 71 that transmits and receives radio waves, a display unit 72, a battery 73, and a data reader 74. In the external display 70, data received by the display-side antenna unit 71 is read by the data reader 74. Then, the data read by the data reader 74 (for example, “discharge side pressure, pump rotation speed, electric energy, integrated value of electric energy, cartridge replacement time, and pump stop”) Information) is displayed on the display unit 72. The battery 73 supplies power to the display-side antenna unit 71, the data reader 74, and the display unit 72.

  As the external display device 70, for example, a general-purpose terminal device such as a smartphone, a mobile phone, a personal computer, or a tablet may be used, or a dedicated terminal device such as a remote monitor may be used. In particular, if a general-purpose terminal device such as a smartphone is used as an external display, the cost of producing a dedicated display can be reduced, so that the cost of the water supply device can be reduced. In addition, since a plurality of users can display the state of the water supply device on each general-purpose terminal device, it is possible to provide a display operation according to the user's level or purpose. For example, it is possible to provide a water supply apparatus that can inform a user who does not have specialized knowledge about the water supply apparatus such as a condominium or building manager in an easy-to-understand manner regarding information related to pump control.

  The external display device 70 is connected to the control unit 40-3 by a near field communication (NFC) technology. More specifically, when the display-side antenna unit 71 generates a radio wave in a state where the external display 70 is close to the control unit 40-3, the control-side antenna unit 67 receives the radio wave, and the control-side antenna The unit 67 converts radio waves into electric power. This electric power is supplied to the integrated circuit 68 and the storage unit 47 to drive the integrated circuit 68 and the storage unit 47. The integrated circuit 68 reads the data stored in the storage unit 47 and sends the data to the control unit side antenna unit 67. The control unit side antenna unit 67 transmits radio waves together with data to the display unit side antenna unit 71. The data reader 74 reads data received by the display-side antenna unit 71 and causes the display unit 72 to display the data.

  The external display device 70 may include a clear button 76 for erasing the display and a reset button (not shown) for resetting data. When the user presses the clear button 76, the information displayed on the display unit 72 (for example, “discharge side pressure, pump speed, electric energy, integrated value of electric energy, cartridge replacement time, The message “The pump has been stopped” is deleted. Further, when the reset button is pressed, a reset signal is transmitted to the control unit 40-3, and the control unit 40-3 that has received the reset signal clears, for example, an integrated value of the electric energy to 0, and displays a replacement time or pump Release the stop. The clear button 76 in the illustrated example is a virtual button that appears on the screen of the display unit 72, but the clear button 76 may be a mechanical button provided outside the display unit 72. The control unit 40-3 does not include a clear button, but the control unit 40-3 may include a clear button and a reset button.

  Note that operation for clearing the display and resetting the data may be provided. Specifically, a clear button 76 is provided on the external display 81 used mainly by the user, and a reset button is provided on the control unit 40-3 used mainly by maintenance personnel. Thus, by providing the reset button only in the control unit 40-3, it is possible to prevent erroneous operation of the reset button by the user who operates the external display device 81. By providing the external display 81 instead of a complicated method of canceling use restrictions such as passwords, it is possible to prevent a reset due to an erroneous operation by the user.

  In the second modified example, data stored in the storage unit 47 of the control unit 40 (for example, “discharge side pressure, pump rotation speed, electric energy, integrated value of electric energy, cartridge replacement timing, Display data including “the pump has been stopped” and the like is transmitted from the control unit 40-3 to the external display unit 70 by wireless communication. Even when the water supply apparatus is not turned on, the control unit side antenna unit 67 can generate power from the radio wave emitted from the external display device 81 and drive the integrated circuit 68 and the storage unit 47. Therefore, even when power is not supplied to the control unit 40-3 during maintenance of the water supply device, the external display device 70 can acquire and display data from the storage unit 47 of the control unit 40-3. .

  NFC is a technology for mutual communication at a short distance of several centimeters. Therefore, when displaying various types of information on the external display 70, the user and the maintenance staff bring the external display 70 close to the control unit 40-3 to a distance that allows mutual communication. This means that when operating the external display 70, the user and maintenance personnel are near the water supply device. For this reason, it leads to preventing the unexpected operation | movement of the water supply equipment resulting from misoperation, for example, resetting the integrated value of electric energy during the cartridge replacement | exchange work of a radioactive substance adsorption | suction part, and starting a pump. In addition, at a site where a plurality of water supply devices are installed, mutual communication is possible at a short distance of the water supply device to be displayed, so that it is possible to prevent an erroneous display of displaying the state of another unintended water supply device. I can do it.

  In the above example, NFC is given as an example of a wireless communication system between the control unit 40-3 and the external display 70. However, any other system such as Bluetooth (registered trademark) and Wi-Fi can be used. Wireless communication can be used. However, NFC is advantageous in that communication can be completed simply by bringing the control unit 40-3 and the external display 70 close to each other. Further, the control unit 40-3 and the external display device 70 may perform wired communication. For example, the control unit 40-3 is provided with an external connection terminal such as a USB (Universal Serial Bus), for example, instead of the control unit side antenna unit 67. May be possible.

(Other configurations)
FIG. 14 is a diagram for explaining a strainer that can be installed in each embodiment of the present invention as described above, for example. For example, as shown in the drawing, in the first embodiment, in the introduction pipe 110, a strainer 1401 can be provided upstream of the radioactive substance adsorbing unit 140. The strainer 1401 removes suspended matter from the water before reaching the radioactive substance adsorbing unit 140 and prevents clogging of the cartridge or filter included in the radioactive substance adsorbing unit 140. From this point of view, the strainer 1401 is desirably finer than the cartridge or filter of the radioactive substance adsorbing unit 140. Further, since the strainer 1401 is expected to be clogged before the radioactive substance adsorbing unit 140 due to the fine eyes, the strainer 1401 can be replaced independently of the radioactive substance adsorbing unit 140. It is desirable to be attached to the introduction pipe 110. In addition, although the radioactive substance adsorption | suction part 140 in 1st Embodiment is illustrated in the figure, similarly in 2nd-10th embodiment, it is possible to provide the strainer 1401 upstream of the radioactive substance adsorption part 140. is there.

  The preferred embodiments of the present invention have been described in detail above with reference to the accompanying drawings, but the technical scope of the present invention is not limited to such examples. It is obvious that a person having ordinary knowledge in the technical field of the present invention can come up with various changes or modifications within the scope of the technical idea described in the claims. Of course, it is understood that it belongs to the technical scope of the present invention.

DESCRIPTION OF SYMBOLS 10 Main water pipe 20 Water supply tap 30 Well 40 Control part 100,200,300a, 300b Water supply equipment 110,310a, 310b Introduction pipe 111 Check valve 112 Inflow valve 120 Water receiving tank 122 Water level gauge 130 Water supply pipe 131 Pump 140,240, 340 Radioactive substance adsorbing part 400a, 400b Water supply equipment 410a, 410b Inlet pipe 411 Check valve 412 Inflow valve 420 Radioactive substance adsorbing part 430a, 430b Water supply pipe 431 Pump 500 Water supply equipment 510 Introducing pipe 520 Radioactive substance adsorbing part 530 Water supply pipe 600, 700a to 700e, 800a to 800c, 900, 1000 Water supply equipment 601 Pressurizing pump 701, 702, 708 Radiation measurement sensor 707 Remote monitoring device 801, 804 Return pipe 802, 805 Switching valve 803 Radioactive substance adsorption 901 Pressure sensor 1021 Connecting pipe 1022 Gate valve 1401 Strainer 1110 First introduction pipe 1210 Second introduction pipe 1030 Water supply pipe

Claims (13)

A pump with the suction side connected to the water receiving tank and the discharge side connected to the water supply pipe;
A pressure sensor for measuring the discharge side pressure of the pump;
A radioactive substance adsorbing portion provided in an introduction pipe for supplying water to the water receiving tank;
A control unit that includes an input unit from the pressure sensor, performs control of the pump, acquires a use amount index of water supply equipment, and executes a determination regarding a maintenance timing of the radioactive substance adsorbing unit based on the use amount index When,
Water supply equipment comprising. A pump having a suction side connected to an introduction pipe communicating with a water supply source and a discharge side connected to a water supply pipe;
A pressure sensor for measuring the discharge side pressure of the pump;
A radioactive substance adsorbing portion provided in the introduction pipe or the water supply pipe;
A control unit that includes an input unit from the pressure sensor, performs control of the pump, acquires a use amount index of water supply equipment, and executes a determination regarding a maintenance timing of the radioactive substance adsorbing unit based on the use amount index When,
Water supply equipment comprising. The usage index is
Including a cumulative flow rate in the introduction pipe or the water supply pipe,
The water supply equipment according to claim 1 or 2. The cumulative flow rate is
Calculated based on the number of rotations of the pump and the pressure measured by the pressure sensor,
The water supply equipment according to claim 3. The usage index is
Including the cumulative operating time of the water supply equipment,
The water supply equipment according to any one of claims 1 to 4. The control unit further includes an input unit of a radiation measurement sensor that measures the radiation dose of the water supply pipe,
The water supply facility according to claim 1 or 2, wherein the usage amount index is a radiation amount of the water supply pipe. The usage index is
It is reset when maintenance of the radioactive substance adsorbing unit is performed,
The water supply equipment according to any one of claims 1 to 6. The determination regarding the maintenance time is as follows:
Including determining whether the usage indicator has reached a first threshold;
The controller is
An output unit configured to output information indicating that the maintenance time has arrived when it is determined that the usage index has reached a first threshold;
The water supply equipment according to any one of claims 1 to 7. The control unit has a second threshold value that is larger than the first threshold value, and determines whether the usage amount index has reached the second threshold value,
The water supply equipment according to any one of claims 1 to 8, wherein water supply to a water supply destination is stopped when the usage amount index reaches a second threshold value.   The water supply facility according to any one of claims 1 to 9, further comprising a display unit that displays information indicating that the maintenance time has arrived or information related to control of the pump.   The said control part is further provided with the communication part comprised so that the information which shows that the said maintenance time came, or the information regarding the control of the said pump was transmitted to an external indicator. The water supply equipment according to item 1.   The water supply facility according to claim 11, wherein the communication unit is a control unit side antenna unit that receives radio waves from the external display and converts the radio waves into electric power.   The water supply facility according to claim 11 or 12, wherein the communication unit transmits the information to the external display by near field communication (NFC).

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