LT5395B - A transferring device of reactor fuel of nuclear power station - Google Patents

Abstract

The invention relates to equipment of a nuclear power station with two or more power bloc for fuel transfer. A device for transfer a reactor fuel of a nuclear power station comprises a receiving - transferring unit in each power bloc, wherein a first end sector is connected to transferring manipulators of thermal assemblies and other elements in energetic bloc. A second end sectors are connected by link of two receiving - transferring units.

Description

The present invention relates to devices for reloading nuclear reactor fuel and can be applied to two or more power units in nuclear power plants (NPPs).

Known reactor reloading plant at Gesen NPP (Switzerland) (see Kncenee B.B. h, ap. CncTeMbi neperpy3KH τοππηββ βολο - βοληηβιχ peaKTopoB. ATOMHaa TexHHKa 3a py6e> K0M, 1983, ετ). Each unit in the nuclear power plant unit provides a set of facilities for transportation and technology operations with thermal assemblies (NEs) and other elements of the reactor core of the power plant unit, such as water filled storage pools (SB) with shelving for new and used thermal assemblies. ; a transfer machine - a manipulator operating directly at the reactor; a conveyor tube with a sealed chamber and receiving transfer gateways passing through the reactor sheath, two devices for positioning containers with thermal assemblies; a receiving / transmitting unit having one end section connected to a single positioning device and the other to vehicles supplying to the power unit new and removed heat sets and other elements of the core.

Since the complexes of the transport and technology operations of the individual units of the nuclear power plant are interconnected, the operation of the whole unit can be examined on the basis of one reactor work. For example, the movement of new thermal assemblies proceeds as follows. One such thermal set is taken from the rack in the storage pool hall by a bridge crane for reception / transfer, placed in a container and transferred to the first positioning device in the pool on the outside of the storage pool reactor shield. Next, the first positioning device changes the position of the container with the new thermal collector from vertical to horizontal and transfers it to a transport tube, which is equipped with product transfer through receiving-transfer sluices and a sealed chamber of the storage pool under the reactor shield. At the other end of the conveying pipe, a container with a new heat sink is taken over by a second positioning device, which changes its position from horizontal to vertical and transfers it to the transfer machine. This machine removes a new heat set from the container and places it in the reactor core instead of the used heat set according to the coordinates. The reverse path of the used thermal assembly is exactly the same. Typically, such thermal assemblies are removed from the core and placed in temporary storage under the reactor shield in the storage basin before any new SH is loaded into the core. If necessary, the reloading machine puts the spent heat set into the transport container and transmits it to the second positioning device, which puts the container from a vertical position into a horizontal position. The container with the spent NE is then transferred to the first positioning device via the receive-transfer gateways, the sealed chamber and the transport tube. Here, the container with the spent NE is re-positioned in a horizontal position and a bridge crane on the receiving / transmitting unit is placed on the SB rack on the outer side of the reactor shroud for temporary storage until removed from the power unit or the entire power site.

The drawback of the device analogue is the lack of technical means that would allow the efficient use of SR fissionable materials in the power plant during decommissioning. The problem is that as the SRs used in the water-in-water reactor are replaced with new NEs, each batch accounting for about one-third of the total number of NEs in the core, stopping reactors for conservation and dismantling . Therefore, in addition to the economic losses associated with the decommissioning of heat and electricity at any NPP reactor, the fact that the reactor is shut down with the intention of decommissioning will result in additional losses.

As a prototype of the invention, we will analyze the Leningrad NPP, Russia, channeled water-graphite reactor reloader [7 Ioane> Kajib H.A., EMejib «HOB H JI. KaHajibHbiū fląepHbiū OHepreTHmecKHH peaicrop. - M., Ατομη3Λ8τ, 1980, στρ. 182-189 (N.A. Dolležal, I.J. Jemeljanov. Channel Nuclear Reactor. - M., Atomizdat, 1980, p. 182189)]. This unit has an unloading-loading machine (IPM) in each power unit, which wraps the new NE into a dedicated security tunnel, which then hermetically connects to the established technology channel, replacing the used NE with a new one, and sealing the used channel with the new NE The NE unloads into an intermediate transport container (box) and into a water-filled SB, a trolley carrying underwater NE boxes between the SB and IPM, racks for used and new NE storage, and a receiving-transfer unit with one end section coupled to a manipulator transport and technology operations within the power unit, and the other with vehicles supplying new power units to the power unit and disposing of used NEs and other core components.

Since the complexes of transport and technological operations of the technical units of separate NPP units are not interrelated, the operation of the whole unit prototype and the unit analogue can be examined on the basis of one reactor work. For example, the movement of new NEs follows the following path: SB Hall Rack - Receiver-Transfer Node Bridge Crane - SB Box NE - Trolley for NE Box Transfer to IPM - IPM. Subsequently used NE in the relevant reactor process channel is replaced by a new IPM. Excerpts from the reactor used in SR, its path is as follows: IPM - SB box NE in a wheelchair, the de ³ EN 5395 B land with NE transported between SB and IPM - reception-transmission unit overhead crane - SB rack used in the NE for temporary storage.

The disadvantage of the installation-prototype, as well as the installation-analogue, is that there are no technical measures that can ensure the efficient use of the SR fissionable materials in the NPP at the stage when any reactor is decommissioned. While the reactor water-graphite reactor NE power output is approximately evenly distributed in the range from near zero to near nominal, about half of the fissionable material remains unburned in the core during reactor shutdown, canning, and dismantling.

The object of the invention is to reduce the economic losses associated with the decommissioning of separated NPP reactors.

The use of the invention enables complete combustion of the spent nuclear reactor SR in the operating unit of the NPP; to use the serviceable components of the decommissioned reactor core (neutron rod-absorbers, energy release control sensors, etc.) in the operating unit of the NPP; to reduce the total amount of radioactive products to be disposed of or disposed of in NPP.

This technical result is achieved by the fact that at least two receiving units of the receiving unit of the unit are connected by a chain of transport of radioactive products removed from the reactor. This link, which ensures the interconnection of the reception-sales nodes, can be in the form of a transport pipeline or a mobile platform with a transport container, which has a layer of biological protection.

The transport chain allows the transport of radioactive materials (incompletely used NE, part time neutron rod-absorbers, energy release control sensors and other elements of the core) from a shut down reactor power unit receiving-transfer unit to a functioning reactor power unit receiving operation unit. In this case, the total amount of radioactive products to be disposed of or disposed of in the NPP is reduced.

The invention will be explained in accordance with the drawing of the available NPP fuel transfer unit. It corresponds to the first embodiment of the above-mentioned circuit application, which ensures the interaction of different reactor receiving-transfer units. The drawing shows: 1 - Reactor Power Unit Unit A Unit 1 (only the part of this unit necessary to explain the invention is marked); 2 - NPP Unit 2 reactor power unit for refueling; 3 - Transport corridor or pipe connecting I and 2; 4- Transport pipe 3 receiving gate on side 1 of the complex; 5 - the transport pipe 3 an acceptance gateway of two complex side (4 and 5, the gateway of the corresponding taking-over node rear sections of the drawing fully shown), 6 - trolley for containers with NE transport on ^four LT 5395 B pipe 7 - rails, carrying 6 carriages; 8 - trolley drives consisting of 9, 10 rollers and 11, 12 guiding drums with 13, 14 synchronous electric motors, flexible steel band; 15 - Container with SH; 16-15 container support rod having a pivoting capability of +/- 90 ° with respect to the container axis, locking this angle in the free position, 17-16 stem head; 18 - remote controlled crane lock for transporting products, not shown in the drawing; 19 - Product grab levers as 18 locking actuator; 20-18 locking cable suspension; 21 and 22 - water filled SB supporting metal structures with racks and slots for storage of containers with NEs in complexes 1 and 2; 23 and 24 are the outer walls of energy blocks, which limit the placement of 1, 2 complexes.

The listed items provide the possibility of transporting the containers with the reactor pulled from the reactor NE from complex 1 to complex 2 as well as backwards.

The transport tube 3 between the receiving and transfer nodes of the complexes 1, 2 (walls of power units 23, 24) and the gates 4, 5 can be made of any material providing the necessary rigidity, waterproof and effective biological protection of the personnel from ionized radiation. The source of such radiation is a container pulled from the reactor NE. The inner cavity of 3, 4, 5 cells is transported for NE cooling and additional protection of personnel against ionized radiation filled with water; if necessary, this water can be drained and refilled with fittings, not shown in the drawing. The approximate length of the transport pipe for the NPP where water-graphite reactors are used, within a square up to 2 m across the cross-section, will be several hundred meters, bearing in mind the presence of an appropriate system of supporting structures, not shown in the drawing.

The transport container is constructed in such a way that the enclosed ND with suspension cannot be folded or damaged when the container is moved from the vertical position to the horizontal and vice versa, it has a support only at two extreme locations over the length. In this sense, the container 15 differs from the intermediate containers used in the NPP where it is a water-graphite reactor which has relatively greater flexibility. In addition to the increased stiffness, the container design provides the capability of NW water cooling both when pulling this container out of the SB or from the 4, 5 locks, and after it is placed in the trolley. The approximate length for the insertion of the container NW with a suspension NPP using water-graphite reactors will be 16 m, the container dimensions through a cross-section within 0.3 m square.

It is assumed that the remote control of the lock 18 with the catches 19 of the transported articles is controlled by the set lock 18 by a water actuator acting on changing the water pressure in the connection lock hose, not shown in the drawing with zero water pressure hoses 19 closed, no water consumption at low hose For the water pressure 19, the levers are also closed, but water poured outwards can be used to cool the product being transported, with high water pressure in the hose, the levers 19 open and the water spill channel is covered (product transport not possible, no cooling required).

The transfer of the heat assemblies (more precisely the container with the NE) from the first 1 to the second complex 2 is carried out as follows:

- raising the water pressure in the hose of the connection lock 18 to a level at which the levers 19 open;

- using the crane hanger 20 of the receiving / transmitting unit, the lock 18 is moved to position A, which coincides with the axis 15 of the NE container 15, the container is located in slot IB of the rack 21,

- by extending the suspension 20, the lock 18 is lowered until the inner center of the levers 19 coincides with the center 17 of the head 17 of the NE container container rod;

- reducing the pressure of the water in the hose of the connection lock 18 to an intermediate level at which the levers 19 close by pulling the head 17 of the container with the NE rod 16, thereby directing the water flowing from the hose to the NE container;

- by means of the suspension 20, the container with the NE is removed from the slot IB of the rack 21 and raised to such a level that its lower part is above the upper edge of the lock 4, where the carriage 6 is located;

- using the suspension 20, the container with the NE is moved to a coordinate which (in the plan) corresponds to one of the special ends of the bogie 6 and is lowered until it comes into contact with it;

- by extending the suspension 20 and moving it along the axis of the lock 4 and bogie 6, the container 15 with the NE (resting on one point) is initially tilted (position B of the suspension 20) and then placed horizontally on the bogie 6;

- raising the water pressure in the hose of the connection lock 18 to the level at which the levers 19 open by releasing the head 17 of the container with the SH bar 16,

- lock 18 hanger 20 lifted (position C), container with NE remains in trolley 6; Rod 16 remains upright,

- the synchronously controlled trolley conveyor motors 13, 14 are actuated, at which time the conveyor belt 8, pulled over the guide wheel 9, unwinds from the drum 11, at the same time the same belt, pushed through the guide wheel 10, rolls onto the drum 12, 15 the transport pipeline 3 starts to move from the lock 4 towards the lock 5 wherever it stops, the transport engines 13, 14 are disconnected,

- the trolley 6 of the container with a rod 16 NE 17privedamas second heads 2 the taking-over of the complex suspension crane 20 lock 18 using the suspension lever ⁶ 20 LT 5395 B 19 beings to grab the container 15 the head 17, the container is raised from the horizontal position to the vertical. It is then raised above the top edge of the lock. The container is moved to slot 22 of the complex ΓΒ rack; later the levers 19 are opened and the container with the NE is left for use in the assembly 2; the lock 19 is raised by the clamp 20 and left in any position.

This completes the cycle of NE shipment from the first 1 to the second 2 complex. The transfer of the above or other materials from the second 2 to the first 1 is carried out analogously.

The second method of transferring radioactive elements, by combining the receiving and transmitting equipment of NPP 1 and 2 complexes, requires no further explanation for simplicity. As mentioned above, it is a mobile platform with a transport container fitted with a bio-protective layer; Requirements for this design include stability, absorption (suppression) of ionizing particles emitted by transported products, ability to temporarily change the position of the container from horizontal to vertical, while not exceeding the allowable length of the container, and the ability to cool and seal the inner part of the container. materials transported. They are placed and removed by placing the container in an upright position. The technical solutions required to perform these operations are known.

Claims (3)

DEFINITION OF INVENTION 1. A reactor fuel transfer unit for a nuclear power plant having a receiving-transfer unit in each power unit, wherein the first end section is coupled to a manipulator for transferring heat assemblies and other core elements within the power unit, wherein the second end section is at least two receiving-transfer units. are connected by a link for transport from a decommissioned power unit to a functioning radioactive product reactor which has not exhausted its resources. 2. A fuel transfer device according to claim 1, characterized in that the link providing interconnection between the receiving and transmitting nodes is a conveying tube with biological protection. 3. A fuel transfer device according to claim 1, characterized in that the link providing the interchange between the receiving and transmitting nodes is a movable platform with a transport container having biological protection.