WO1997004462A1

WO1997004462A1 - Miniaturized nuclear reactor utilizing improved pressure tube structural members

Info

Publication number: WO1997004462A1
Application number: PCT/US1995/009189
Authority: WO
Inventors: Sigmunt Rottenberg
Original assignee: Individual
Current assignee: Individual
Priority date: 1995-07-19
Filing date: 1995-07-19
Publication date: 1997-02-06
Anticipated expiration: 1998-01-19
Also published as: CA2197419A1

Abstract

The present invention relates to a miniaturized nuclear reactor utilizing improved pressure tube structural members comprising: a moderator containing one calandria tube (12) contained within the moderator (20); one fuel channel pressure tube (14) contained within the one calandria tube (12); one fuel bundle (26) contained within the one fuel channel pressure tube (14); one fuel channel pressure tube pad (18) positioned between the one calandria tube (12) and the one fuel channel pressure tube (14); one horizontal exterior support pad (30) positioned on the bottom reactor wall, one fuel bundle pad (16) positioned between the one fuel bundle (26) and the one fuel channel pressure tube (14); one vertical support pad (24) positioned on a reactor side wall between the one calandria tube (12) and the reactor side wall; one angular support pad (28) positioned on a corner formed between the reactor top wall and the reactor side wall.

Description

MINIATURIZED NUCLEAR REACTOR UTILIZING IMPROVED PRESSURE TUBE STRUCTURAL MEMBERS

SUMMARY OF THE INVENTION

The present invention describes new shapes of fuel tubes. The advantages are that the fuel tubes are stronger and less brittle, there is more suiface contact area for heat exchange to take place and therefore, the tubes' new shape is more efficient

For purposes of miniaturization, the fuel tube can be made from any type of material- metal, metal alloys, ceramic, glass, fiberglass, carbon-graphite, epoxy and/or plastic composites or a combination of these materials with or without reinforcements. The surfaces could be enameled, coated, lined and/or cladded. The shapes would be most applicable to the miniaturization, but could be used in the larger scale reactors.

In the present invention, novel fuel bundles for use in miniaturized reactor are described. The novel fuel tube design is to solve partially the problem of disposal of the spent fuel. The secondary benefit is the increased safety of operation of the reactor, in case of accidental meltdown.

The present invention describes novel Support pads to hold the fuel tubes in place. The pads are of different shapes and sizes. Pads provide continuous support, intermediate support, are integral with Structural Member and are inserted inside the fuel tube. The pads are applicable to miniaturization. All surfaces and parts of the reactor and/or fuel tubes could be coated, cladded, enameled or lined.

The rolled joint connection at the end of the fuel channel pressure tube (FCPT) was developed to -aci-titate removal and replacement of the fuel channel pressure tube (FCPT). This is important in design of miniaturized reactors and in maintenance of all integral parts contained therein

The advantages of d e novel Structural Member Metal Tubes are as follows:

1. PROTECTION OF SURFACE BY LINING OR COATING

The interior surface and odier integral parts contained therein can be further protected by adding a protective coating or Hning of the interior surface ofthe member metal tube, to prevent iiradiarion ofthe metal tube from the FCPT. The coating or lining of the interior surface should be of a material inert to irradiation to provide positive protection. The use of coating, lining, etc. is novel and can be implemented because of the novel design of the novel Structural Metal Member. The deflection and bending stresses inherent therein would be nominal with the present design ofthe invention. Therefore, the coating or lining would not develop cracks, peel or other structural and/or functional defects.

In the prior art, routinely, the calandria tube would deflect and bend to the extent that some coating or uning could not have been used. This obvious disadvantage would be overcome by the present invention

2. FUEL CHANNEL PRESSURE TUBE (FCPT)

The present invention reduces friction for movement of expansion and/or rotation of the fuel channel pressure tubes as follows:

A) FCPT made from ceramic or any Irradiation-Inert Material such as glass, fiberglass, carbon- graphite, epoxy, metal alloys, or plastic composites in accord with the following features:

1. Coat exterior surface of the FCPT to reduce friction around the FCPT.

2. Provide steel bends where the FCPT comes in contact with intermediate support pads.

3. Coat the steel bends.

B) FCPT Made From Metal Subject to Irradiation in accord with the following features:

1. Coat exterior surface of the FCPT to reduce friction.

2. Coat to prevent irradiation of support pads and spacers.

3. Coat the ends of the FCPT to prevent irradiation of the tube extension at connection with FCPT.

3. NEWSUPPORTPADSANDSPACERS

The support pads inserts are one-piece made full length (20) feet of FCPT to be inserted into the new structural metal member inside the tubes. The support pads once inserted to be fastened to the new structural metal member. The f astener(s) should prevent the sliding of the pad out of position. The spacers could be intermittently spaced and do not have to be the full length. They would be held in position by being attached to the full length support pad or attached to the new structural metal member. The support pads could be an integral part of the new structural metal member. The configuration where the web of member penetrates to the inside of the tube as depicted in the drawings. The part projecting part inside the tube to be shaped as support pad or as spacer depending on location.

4. SUPPORTPADSANDSEPARATORFORFCPT

A) FCPT Made of Ceramic, etc.

1. The support pads and separators could be made of metal and/or metal alloys.

2. The metal should be coated at contact with the FCPT to reduce friction.

3. The pads should be grooved or have depressions to allow for circulation and cooling.

B) FCPT Made of Metal

1. The support pads and separators should be made out of material ( ceramic, glass, etc.) are inert to irradiation from FCPT.

2. The metal support pads and superstars should be coated or lined with material inert irradiation from FCPT.

3. The surface of support pad and separators in contact with FCPT should be coated to reduce friction.

4. The pads should be grooved or have depressions to allow for circulation and cooling.

C) FUEL BUNDLES- SUPPORT PADS INSIDE THE FCPT

The fuel bundles inside the FCPT rest directly on the bottom of the tube. The fuel bundles should rest on pads to protect the surface of the FCPT from abrasion, wear and tear. The abrasion is caused by the fuel bundles sliding during loading and unloading and due to the ebngation ofthe FCPT and vibration, etc. The pads would have a shape of rails (two) fiill length ofthe FCPT secured at ends against moving out of position. The pads should be used with the FCPT made from metal, ceramic, glass, etc. The pads would also protect the ceramic and glass FCPT from Chipping and cracking. 5. FCPT MADE OUT OF GLASS

Advantages of using glass for making the fiiel channel pressure tubes. The use would increase safety and reduce radiation emission in case of a meltdown. The glass, during the extreme heat due to meltdown, would not melt The melted glass would encapsulate the fuel bundles and pellets. This would reduce radiation emission from the nuclear fuel and contamination of parts of the reactor. It would minimize the damage to the FCPT affected by meltdown and allow for repairs of the reactor by replacement of the FCPT affected by the meltdown.

6. THE NOVEL REACTOR UNIT

The new reactor unit would house four, six, or eight FCPT within it, and be used as a reactor. The unit will be a self contained miniature reactor.

The exterior shape is the reactor can be round square, rectangular triangular and polygonal and/or any combination thereof. The tubes as shown in FIGURE 8 are novel calandria tubes resting on support pads.

Inside the calandria tubes are fuel channel pressure tubes. The use of glass for FCPT would have the advantage of safety, and reduction of emission of radiation during a melt down. In case of meltdown, the metal reactor would be encased to prevent radiation passing to the exterior and placed inside a concrete vault similar to a transformer vault in case of malfunction and/or meltdown the radiation will be contained therein.

When the fuel is used up (spent) it wui be removed and replaced to provide continuous service ofthe miniature reactor during normal usage.

The present invention ofthe novel nuclear reactor has support pads for Calandria Tubes. The support pads as shown in FIGURE 7 could be used to support the calandria tubes. The load of the fuel bundles inside the FCPT would be transferred to the Calandria tubes and from the Calandria tubes to the new unit reactor. In addition, the pads could be in the shape of two rails on which the bundles could readily slide.

The present invention describes novel spent fuel disposal. The fuel pellets of spent fuel could be encapsulated in melted glass for disposal. This could be done individually or in bundles. The glass encapsulated fuel would be encased in concrete blocks to be stacked up in storage. The blocks would be made from contaminated (material) concrete, ceramic, and recast into blocks.

The most radioactive is the fuel having a protective shield from a low contaminated material made in shapes for easy shipping, handling and storage. It would be fully automated, requiring no handling by humans. The orderly fashfon of disposal would require less space, be economical and would not represent danger to the surrounding area.

When the fuel is spent,- the fiiel bundles are removed from the reactor. The spent pellets should be removed from the bundles. The pellets should intentionally undergo a meltdown, and in the process, some contaminant be added to prevent reprocessing the spent uranium into a bomb grade material (national security reasons) and the pellets should be encapsulated with a glass coating to reduce radiation emission. The pellets should be placed in a storage container. This container should be --mnufectured from radiation contaminated material. The container could be of metal and/or concrete. The size that could be handles for transport and to put on shelf or warehouse. The process described could be fully automated and done by remote control.

The advantages are that the radiation contaminated material would be utilized and the waste disposal will be done in an orderly and controlled manner. It would reduce the amount of waste, reduce the space to store, and would reduce the amount of radiation from the spent fuel. The controlled and orderly manner of handling and storage would increase safety and protect the environment

The present invention describes disposal of spent fiiel being encased in melted down glass. Could be used to dispose of nuclear wastes. The product would be radioactive glass blocks that would have to be stored for safety. The glass blocks would be stable and would not have radioactive molecules leaking. This would be stable for a very, very long time.

The present invention describes a novel, state of the art fuel bundle. The fuel bundle is approximately 20 inches long and 4 5/8 inches in diameter. The Cylindrical fuel pellets are approximately 3/4 inches long and ^lA inch in diameter. The fuel element is a metal fuel.

In the present invention, the pads are of different shapes and sizes. Pads provide continuous support, intermediate support, are integral with Structural Member and are inserted inside the tube. The pads are applicable to miniaturization.

Another feature of the present invention, is all surfaces and parts could be coated, cladded, enameled, or lined as stated in the text of the first patent and this application.

An additional feature of the present invention is the rolled joint connection at the end of the fuel channel pressure tube was developed to facilitate the removal and replacement of the fiiel channel pressure tube. This is important in design of miniaturized reactors and in maintenance of all other sizes of reactors, and applies to the use ofthe fuel channel pressure tube made of all materials. The spent fuel after second use would be less radioactive. It would pose a lesser problem of storage and handling.

One benefit ofthe present invention is in making use of a currently discarded material namely spent fuel in highly radioactive state.

An additional benefit of the present invention is in reduction of storage volume of highly radioactive spent fueL The spent fuel should be used as fuel for "heating" the hot water produced by the second use of fuel in the i-ji-criin-aiurized reactor, would be passed through a heat exchanger and returned to the reactor. The heated water from the heat exchanger could be used to heat apartment and/or office buildings and/or generate electricity and/or generate heat for green houses to produce. The heated water could be convened to steam and utilized as mechanical energy. The spent fuel after first use is still highly radioactive, but not sufficient for production of electricity. The spent fuel when used the second time is less radioactive, and the reactor would also operate at a lower pressure.

Still another feature of the present invention is addressed to a structural member for nuclear reactor pressure tubes and method which provides effective insertion of water coolant within the recirculating loops of conventional boiling water reactors, but without resorting to complex loop selection logic. Through analysis by modeling and the like of the requirements of the structural member for nuclear reactor pressure tubes in terms of time for complete coolant injection and in terms of the required quantity of injected fluid, flow rates of injection are derived and requisite quantities of coolant are determined and identified such that the structural member for nuclear reactor pressure tubes process is controlled through the simple approach of utilizing flow rate controlling hydraulic resistance within coolant injection conduits. Those hydraulic resistances may be implemented with a conventional orifice, the size and shape of which deteπnines desired flow rates or by the throttling of a valve within the injection conduit achieving the equivalent result Under the process, cross tie conduits and associated cross tie valving otherwise used for recirculation loop selection for coolant injection are not activated, but merely remain in an open condition.

As another feature, the invention provides a structural member for nuclear reactor pressure tubes having a low pressure coolant injection system for a nuclear power facility of a variety having a boiling water reactor, having a reactor core and normal operating pressure, first and second recirculation ops including respective first and second recirculation pumps and actuable discharge valves, a suppression pool water source, a condensate storage tank, and a safety system responsive to a bss-of-coolant accident to generate a safety output The system includes first and second low pressure coolant injection pumps having suction inputs and discharge outputs and actuable to pump water. A supply conduit arrangement is provided for coupling the suction inputs ofthe first and second low pressure coolant injection pumps in fluid flow communication with the suppression pool. First and second coolant injection conduits are provided which are coupled with respective discharge outputs of the first and second low pressure coolant injection pumps and to respective first and second recirculation loops. First and second hydraulic resistance components within respective first and second coolant injection conduits are provided for restricting the flow of water coolant therein to a predetermined fluid rate selected to deliver a predetermined quantity of water coolant to each of the first and second recirculation loops, the flow rates being selected as effective for carrying out the emergency cooling of the reactor core from one coolant injection conduit. A control arrangement is provided which is responsive to the safety ouφut for actuating the first and second low pressure coolant injection pumps.

As another feature, the invention provides a method for injecting low pressure cooling water into the boiling water reactor of a nuclear power facility having a source of emergency core cooling water, first and second independent recirculation loops noπnally circulating water through the core of the reactor for steam generation and a safety system responsive to a loss-of-coolant accident to generate a safety output for effecting the supply of at least a predetermined quantity of water coolant to the reactor, comprising the steps of:

A) providing first and second water flow paths from the source of water coolant to respective first and second recirculation loops;

B) providing low pressure coolant injection pumps actuable or pumping water from the source through the first and second water flow paths;

C) providing a valve arrangement actuable from a closed to an open condition for effecting flow within the first and second water flow path actuating the valve arrangement in response to the safety output to permit water coolant flow simultaneously in each first and second water flow path; actuating the low pressure coolant injection pumps in response to the safety output; and

D) restricting the flow of the water coolant in each first and second water flow path to a predetermined fluid flow rate selected to deliver the predetermined quantity of water coolant to each respective first and second independent recirculation loops, said flow rate being selected as effective for caπying out the emergency cooling of the reactor core from one water flow path.

As another feature, the invention provides a low pressure coolant injection system for a nuclear power facility of a variety having a boiling water reactor with a reactor core, and normal operating pressure, first and second recirculation loops including respective first and second recirculation pumps and actuable discharge valves, a suppression pool water source, a condensate storage tank, and a safety system responsive to a loss-of-coolant accident to generate a safety output. The system includes first and second low pressure coolant injection pumps having suction inputs and discharge outputs and able to pump water. A supply conduit arrangement is provided for coupling the suction inputs of the first and second low pressure coolant injection pimps in fluid flow communication with the suppression pool and further includes a cross tie conduit arrangement for selectively interconnecting the discharge outputs of the first and second bw pressure coolant injection pumps. First and second coolant injection conduits are provided which are coupled with respective discharge outputs of the first and second low pressure coolant injection pumps and to respective first and second recirculation loops. First and second low pressure coolant injection valves are provided within respective first and second coolant injection conduits and are able between cbsed and open orientations. Further provided are first and second hydraulic resistance devices within respective first and second coolant injection conduits for restricting the flow of water coolant therein to a predetermined fluid rate selected to deliver a predetermined quantity of water to each of the first and second recirculation loops, the flow rate being selected as effective for carrying out the emergency cooling ofthe reactor core from one coolant injection conduit. A cross tie valve arrangement is provided within the cross tie conduit which is able between open and cbsed conditions for selectively directing the ouφuts of the first and second low pressure coolant injection pumps to one ofthe first and second recirculation loops through select first and second coolant injection conduits. A control arrangement is provided which is responsive to the safety output for actuating the first and second low pressure coolant injection pumps, the first and second bw pressure coolant injection valves and retaining the cross tie arrangement in the open condition in the presence ofthe safety output.

The invention, accordingly, comprises the system and method possessing the construction, combination of elements, arrangement of parts and steps which are exemplified in the following description.

Accordingly, it is an object of the present invention to provide a new structural member with metal fuel channel pressure tubes that reduce moment, reaction and deflection stresses at the ends of the metal pressure tubes.

More particularly, it is an object of the present invention to provide a new structural member that will reduce the incidence of cracks developing in the metal of the fuel channel pressure tubes. The new structural member with ceramic fuel channel pressure tubes reduces moment, reaction and deflection stresses at the end of the ceramic pressure tube. The ceramic pressure tube is not affected by irradiation and growth of its diameter as the metal tube is.

In keeping with these objects, and with others which will become apparent hereinafter, one feature of the present invention resides, briefly stated, in the ability to use ceramics instead of metal as the pressure tubes.

When the structural member for nuclear reactor pressure tubes is designed in accordance with the present invention, stress of the pressure tube is greatly reduced, if not eliminated.

In accordance with another feature ofthe present invention, the invention provides for the use of ceramic pressure tubes by providing fiill length support without deflection for ceramic brittle material.

Another feature ofthe present invention is that the new structural member would be made to house four, six or eight, etc. pressure tubes within it The new structural member would act as a Calandria for all the pressure tubes within. The advantage would be that the new structural member would act as a unit that would nave its own controls as to the flow of gas or heavy water. It could be taken out of service for maintenance or pressure tube replacement, while the reactor would remain in operation.

Yet another feature of the present invention is the support pads which cradle the pressure tubes and prevent sideways movement of the tube.

Accordingly, it is a general object ofthe present invention to provide the reduction of stresses in Calandria and pressure tubes.

It is a more particular object of the present invention to provide continuous and intermittent support for the pressure tubes.

An object ofthe present invention is to provide the prevention of cracks in the pressure tubes.

A further object of the present invention is to eliminate deflection and sag in Calandria and pressure tubes.

A still further object ofthe invention is to provide the use of materials for pressure tubes that withstand irradiation, high temperatures, etc (ceramic). A further object ofthe present invention is to allow for replacement of pressure tubes without shutting down the reactor.

Accordingly, it is an object of the present invention to provide that the End plates of glass or metal will be foimed with depressions to fit and accept the ends of the Fuel elements.

More particularly, it is an object of the present invention to provide a Hollow tube to be placed between the End plates for the length of the fuel bundle. A rod or wire will be threaded through the tube and through a hole in the end plates. After the Fuel elements will be in place in the End plates the rod or wire will be reissued and anchored to hold the bundle together.

In keeping with these objects, and with others which will become apparent hereinafter, one feature of the present invention resides, briefly stated, in the end of the tube or rod there will be a spacer plate. The spacer Plate will be in contact with the inside face of the End plates. The stress ofthe rod or wire will hold the bundle together, but it will not put stress on the Glass Fuel elements.

When the fuel bundle is designed in accordance with the present invention, after the bundle is removed from the reactor, the end plates can be separated from the bundle and reused. The Fuel elements with the spent fuel could be removed and sent to storage.

Still another feature ofthe present invention is that The End plate , made of glass or metal will be formed to leave cup-like indentions to fit to accept the ends of the Fuel elements.

Yet still another feature of the present invention is that The End plate, made of glass, will be (welded) attached to the Fuel elements by molten glass.

Still yet another feature ofthe present invention is that the End plate holding the fuel elements together will also be made of glass.

Another feature of the present invention is that the Fuel elements will be assembled into a bundle.

Yet another feature ofthe present invention is that the Fuel elements will be made of glass and filled with pellets.

Still another feature ofthe present invention is that At Each end, a plate is welded to the Fuel elements, holding them together as a bundle.

Yet still another feature of the present invention is that Approximately Thirty-Seven of the Fuel elements form a cylindrical Fuel Bundle.

Still yet another feature ofthe present invention is that the Fuel Pellets are stocked end to end inside the cylindrical Fuel Element container and sealed.

Another feature ofthe present invention is that the Fuel element is a metal Fuel Sheathing, a cylinder of approximately twenty inch length and 5/8 inch diameter.

Yet another feature ofthe present invention is that Cylindrical Fuel pellets approximately 3/4 inches long and Y. inch in diameter.

Still another feature ofthe present invention is that The Fuel Bundle is approximately twenty inches long and 45/8 inches in diameter.

The present invention is addressed to a structural member for nuclear reactor pressure tubes and method which provides effective insertion of water coolant within the recirculating loops of conventional boiling water reactors, but without resorting to complex loop selection logic. Through analysis by modeling and the like of the requirements of the a structural member for nuclear reactor pressure tubes in terms of time for complete coolant injection and in terms of the required quantity of injected fluid, flow rates of injection are derived and requisite quantities of coolant are deteimined and identified such that the a structural member for nuclear reactor pressure tubes process is controlled through the simple approach of utilizing flow rate controlling hydraulic resistance within coolant injection conduits. Those hydraulic resistances may be implemented with a conventional orifice, the size and shape of which determines desired flow rates or by the throttling of a valve within the injection conduit achieving the equivalent result Under the process, cross tie conduits and associated cross tie valving otherwise used for recirculation loop selection for coolant injection are not activated, but merely remain in an open condition, under the new method and system, necessaiy a structural member for nuclear reactor pressure tubes modifications are achieved without resort to the complicated system and instrumentation otherwise required for loop selection with a minimum of hardware perturbation, rewiring or repiping.

As another feature, the invention provides a structural member for nuclear reactor pressure tubes having a low pressure coolant injection system for a nuclear power facility of a variety having a boiling water reactor, having a reactor core and normal operating pressure, first and second recirculation loops including respective first and second recirculation pumps and able discharge valves, a suppression pool water source, a condensate storage tank, and a safety system responsive to a bss-of-coolant accident to generate a safety output The system includes first and second bw pressure coolant injection pumps having suction inputs and discharge outputs and able to pump water. A supply conduit arrangement is provided for coupling the suction inputs of the first and second low pressure coolant injection pumps in fluid flow communication with the suppression pool. First and second coolant injection conduits are provided which are coupled with respective discharge outputs of the first and second low pressure coolant injection pumps and to respective first and second recirculation loops. First and second hydraulic resistance components within respective first and second coolant injection conduits are provided for restricting the flow of water coolant therein to a predetermined fluid rate selected to deliver a predetermined quantity of water coolant to each of the first and second recirculation loops, the flow rates being selected as effective for carrying out the emergency cooling of the reactor core from one coolant injection conduit. A control arrangement is provided which is responsive to the safety output for actuating the first and second low pressure coolant injection pumps.

As another feature, the invention provides a method for injecting low pressure cooling water into the boiling water reactor of a nuclear power facility having a source of emergency core cooling water, first and second independent recirculation loops normally circulating water through the core of the reactor for steam generation and a safety system responsive to a loss-of-coolant accident to generate a safety output for effecting the supply of at least a predetermined quantity of water coolant to the reactor, comprising the steps of: providing first and second water flow paths from the source of water coolant to respective first and second recirculation loops; providing low pressure coolant injection pumps able or pumping water from the source through the first and second water flow paths; providing a valve arrangement able from a cbsed to an open condition for effecting flow within the first and second water flow path acmating the valve arrangement in response to the safety output to permit water coolant flow simultaneously in each first and second water flow path; actuating the low pressure coolant injection pumps in response to the safety output; and restricting the flow of the water coolant in each first and second water flow path to a predetermined fluid flow rate selected to deliver the predeteimined quantity of water coolant to each respective first and second independent recirculation loops, said flow rate being selected as effective for caπying out the emergency cooling of the reactor core from one water flow path.

As another feature, the invention provides a low pressure coolant injection system for a nuclear power facility of a variety having a boiling water reactor with a reactor core, and normal operating pressure, first and second recirculation loops including respective first and second recirculation pumps and able discharge valves, a suppression pool water source, a condensate storage tank, and a safety system responsive to a loss-of-coolant accident to generate a safety output. The system includes first and second low pressure coolant injection pumps having suction inputs and discharge outputs and able to pump water. A supply conduit arrangement is provided for coupling the suction inputs of the first and second low pressure coolant injection pimps in fluid flow communication with the suppression pool and further includes a cross tie conduit arrangement for selectively interconnecting the discharge outputs of the first and second bw pressure coolant injection pumps. First and second coolant injection conduits are provided which are coupled wilh respective discharge outputs of the first and second low pressure coolant injection pumps and to respective first and second recirculation loops. First and second low pressure coolant injection valves are provided within respective first and second coolant injection conduits and are able between cbsed and open orientations. Further provided are first and second hydraulic resistance devices within respective first and second coolant injection conduits for restricting the flow of water coolant therein to a predetermined fluid rate selected to deliver a predetermined quantity of water to each of the first and second recirculation loops, the flow rate being selected as effective for carrying out the emergency cooling ofthe reactor core from one coolant injection conduit. A cross tie valve arrangement is provided within the cross tie conduit which is able between open and cbsed conditions for selectively directing the outputs of the first and second bw pressure coolant injection pumps to one ofthe first and second recirculation loops through select first and second coolant injection conduits. A control arrangement is provided which is responsive to the safety output for actuating the first and second low pressure coolant injection pumps, the first and second bw pressure coolant injection valves and retaining the cross tie arrangement in the open condition in the presence of the safety output.

More particularly, it is an object of the present invention to provide a new structural member that wui reduce the incidence of cracks devebping in the metal of the fuel channel pressure tubes. The new structural member with ceramic fiiel channel pressure tubes reduces moment, reaction and deflection stresses at the end of the ceramic pressure tube. The ceramic pressure tube is not affected by irradiation and growth of its diameter as the metal tube is. In keeping with these objects, and with others which will become apparent hereinafter, one feature of the present invention resides, briefly stated, in the ability to use ceramics instead of metal as the pressure tubes.

In accordance with another feature ofthe present invention, the invention provides for the use of ceramic pressure tubes by providing full length support without deflection for ceramic brittle material.

Another feature ofthe present invention is that the new structural member would be made to house four, six or eight, etc. pressure mbes within it. The new structural member would act as a Calandria for all the pressure mbes within. The advantage would be that the new structural member would act as a unit that would nave its own controls as to the flow of gas or heavy water. It could be taken out of service for maintenance or pressure tube replacement, while the reactor would remain in operation.

It is a more particular object of the present invention to provide continuous and intermittent support for the pressure mbes.

An object ofthe present invention is to provide the prevention of cracks in the pressure mbes.

A further object of the present invention is to eliminate deflection and sag in Calandria and pressure mbes.

A still further object ofthe invention is to provide the use of materials for pressure tubes that withstand iiradiation, high temperatures, etc (ceramic).

A further object ofthe present invention is to allow for replacement of pressure tubes without shutting down the reactor.

The novel features which are considered characteristic for the invention are set forth in the appended claims. The invention itself, however, both as to its construction and its method of operation, together with additional objects and advantages thereof, will be best understood from the following description ofthe specific embodiments when read and understood in connection with the accompanying drawing. DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENT

Firstly, referring to FIGURE 1 which is a diagrammatic view of a miniaturized nuclear reactor 10 utilizing improved fuel channel pressure mbe 14 structural members. The entire miniaturized nuclear reactor 10 is composed of a moderator tank having a moderator inlet and a moderator outiet. The fluid contained within the moderator is circulated throughout the moderator tank by the moderator pump and is cooled in the moderator cooler. An additional coolant system to extract heat from and cool the fuel pressure channel mbes through a coolant duct system is composed of a coolant inlet, coolant outlet having a coolant gas fan. The coolant passes through a heat exchanger which has its own closed heat extraction system utilizing a feed water pump to circulate fluid throughout. The heat exchanger extracts the heat from the coolant utilizing the energy to propel a turbine which generates electricity from a generator. Within the heat exchanger system a condenser is positioned. The heat extracted from this system can heat apartment buildings and/or office buildings and/or green houses as well as generate electricity.

Secondly, referring to FIGURE 2 which is a end perspective view of a miniaturized nuclear reactor 10 utilizing improved fuel channel pressure mbe 14 structural member. The calandria mbes 12 are contained within the moderator 20. The m-uiiaturized nuclear reactor 10 has exterior reactor walls 42 with a matrix of interior partitioning walls: the reactor wall interior horizontal 44 and the reactor wall interior vertical 46. Although in the drawing there only shows four moderator 20 compartments, there may be lesser or more moderator compartments 20 by utilizing additional reactor wall interior horizontal 44 and reactor wall interior vertical 46. The calandria mbes 12 are supported within the moderator 20 on the bottom by horizontal interior support pad 22 which is integrally positioned approximately mid-distance within and extending lengthwise throughout the reactor wall interior horizontal 44. The calandria mbes are supported within the moderator 20 on an inner side by a vertical support pad 24 which is integrally positioned approximately mid-distance within and extending lengthwise throughout the reactor wall interior vertical 46. The calandria tubes are supported within the moderator 20 on an angular inner side by a angular support pad 28 which is integrally positioned within extending lengthwise throughout the corner formed between throughout top and bottom of the reactor walls 42. Within the calandria tube 12, a fuel channel pressure mbe support 18 is positioned at the bottom upon which the fiiel channel pressure mbe 14 rests. At a bottom position within the fiiel channel pressure tube 14, a fuel bundle support pad 16 is simated upon which rests the fuel bundle 26. Now referring to FIGURE 2A which is a front view of the a miniaturized nuclear reactor 10 utilizing improved pressure mbe 14 structural members. The calandria mbes 12 are contained within the moderator 20. The miniaturized nuclear reactor 10 has exterior reactor walls 42 with a matrix of interior partitioning walls: the reactor wall interior horizontal 44 and the reactor wall interior vertical 46. Although in the drawing there only shows four moderator 20 compartments, there may be lesser or more moderator compartments 20 by utilizing additional reactor wall interior horizontal 44 and reactor wall interior vertical 46. The calandria tubes 12 are supported within the moderator 20 on the bottom by horizontal interior support pad 22 which is integrally positioned approximately mid-distance within and extending lengthwise throughout the reactor wall interior horizontal 44. The calandria mbes are supported within the moderator 20 on an inner side by a vertical support pad 24 which is integrally positioned approximately mid-distance within and extending lengthwise throughout the reactor wall interior vertical 46. The calandria mbes 14 are supported within the moderator 20 on an angular inner side by a angular support pad 28 which is integrally positioned within extending lengthwise throughout the comer formed between throughout top and bottom of the reactor walls 42.

Now referring to FIGURE 2B which is an enlarged perspective view of a horizontal interior support pad 22 positioned on reactor wall interior horizontal 44. By resting atop of the horizontal interior support pad 22 on the horizontal interior support pad concave 22D, it holds an upper calandria mbe 12 in place as well as holding a lower calandria mbe 12 in place at its top by positioning in the upper convex surface of the calandria mbe 12 into the horizontal interior support pad concave 22D. The horizontal interior support pad 22 is positioned approximately mid-distance and extends throughout in an interspersed lengthwise fashion of the reactor wall interior horizontal 44. The horizontal interior support pad 22 comprises: horizontal interior support pad proximal end 22A; horizontal interior support pad distal end 22B; horizontal interior support pad groove 22C; and horizontal interior support pad concave 22D. The horizontal interior support pad proximal end 22A is flat and abuts an inner segment of the reactor wall interior horizontal 44. There are two horizontal interior support pad distal ends 22B foiming a horizontal interior support pad groove 22C therebetween.

Referring to FIGURE 2C which is an enlarged front view of an angular support pad 28 affixed to a reactor wall 42. The calandria mbes are supported within the moderator 20 on an angular inner side by a angular support pad 28 which is integrally positioned within extending lengthwise throughout the comer formed between throughout top and bottom of the reactor walls 42. The angular support pad 28 comprises: angular support pad top member 28A and angular suppoπ pad bottom member 28B. The angular support pad top member 28 A abuts the calandria tube 12 and the angular suppoπ pad bottom member 28B is securely affixed within the comer formed between throughout top and bottom of the reactor walls 42.

Refemng now to FIGURE 2D which is an enlarged front view of a vertical support pad 24 positioned in the reactor wall interior vertical 46. By resting on a side of the a vertical support pad 24 on the vertical support pad concave 24D, it holds left calandria tube 12 in place as well as holding a right calandria mbe 12 in place at its top by positioning in the upper convex surface ofthe calandria mbe 12 into the vertical support pad concave 24D located on both sides of the vertical support pad 24. The vertical support pad 24 is positioned approximately mid-distance and extends throughout in an interspersed lengthwise fashion of the reactor wall interior vertical 46. The vertical support pad 24 comprises: a vertical support pad proximal end 24A; vertical support pad distal end 24B; and vertical support pad groove 24C.

The vertical support pad proximal end 24A is flat and abuts an inner segment of the reactor wall interior vertical 46. There are vertical suppoπ pad distal end 24B forming a horizontal interior suppoπ pad groove 22C therebetween. The horizontal interior suppoπ pad groove 22C wraps around an exterior segment ofthe reactor wall interior vertical 46.

Now referring to FIGURE 3 is an enlarged front view of a horizontal exterior suppoπ pad 30 affixed upon the bottom interior surface ofthe reactor wall 42. The horizontal exterior support pad 30 comprises: a horizontal exterior support pad end 30A; a horizontal exterior support pad -fastener 30; and a horizontal exterior support pad concave 30C. The calandria mbe 12 rests atop ofthe horizontal exterior support pad 30 within the horizontal exterior suppoπ pad concave 30C. The horizontal exterior support pad 30 extends at an approximate mid-position throughout in a lengthwise configuration throughout the moderator 20.

Now referring to FIGURE 2F is an enlarged front upper left view of a miniaturized nuclear reactor 10 utilizing improved pressure mbe 14 stmctural member, the fuel bundle 40 rests atop of the fiiel bundle support pad 16 which rests upon the fuel channel pressure mbe 14 which in m rests atop of the fuel channel pressure mbe support pad 18 which rests atop of the calandria mbe 12 which rests atop of the calandria support pad 12. The fuel bundle support pad 16 fr.rn.jng a bridge-like support upon which the fuel bundle 40 rests comprises a pair of fuel bundle support pad spacers 16A which are positioned at distal ends of a fuel bundle support pad strap 16B. The fuel channel pressure mbe support pad 18 comprises: fuel channel pressure mbe pad vertical spacer 18 A; fuel channel pressure mbe pad end 18B and fuel channel pressure mbe pad horizontal spacer 18C. The fuel channel pressure mbe pad end 18B is positioned at an obtuse angle to the fiiel channel pressure mbe pad vertical spacer 18A in order to conform to the interior curvature ofthe calandria tube 12. The fiiel channel pressure mbe support pad 18 may extend throughout the length of the calandria mbe 12.

Referring now to FIGURE 4 which is a front view of a second embodiment fiiel channel pressure mbe 114 exhibiting a plurality of second fiiel channel pressure tube compartments 114A arranged around the exterior periphery of the second fuel channel pressure mbe 114. The second embodiment fuel channel pressure mbes 114 are inserted within the second calandria mbe 112. The plurality of second fiiel channel pressure mbe compartments 114A interlock into the opposingly configured second calandria mbe compartments 112A which are positioned about an interior peripherally ofthe second calandria tube 112.

Referring to FIGURE 4A which is a front view of a second calandria mbe 112. There are second calandria mbe coπpartments 112A positioned about an interior peripherally of the second calandria mbe 112 in and throughout which the second fuel channel pressure mbe compartments 114A slide within.

Now referring to FIGURE 5 and FIGURE 5A which are a perspective view and a cross- sectional view of a second fuel channel pressure tube suppoπ pad 113 comprising: second fuel channel pressure mbe suppoπ pad end 113A; second fuel channel pressure mbe suppoπ pad spacer 113B; second fiiel channel pressure mbe support pad concave 113C; second fuel channel pressure tube suppon pad convex 113D; and second fiiel channel pressure mbe suppon pad groove 113E. The second fuel channel pressure mbe suppoπ pad 113 functions to support the fuel channel pressure mbe 14 and extends full length and attach to the calandria mbe 12 at each end. It is important that the pads are affixed in place. The second fiiel channel pressure mbe support pad concave 113C and the second fuel channel pressure mbe support pad convex 113D have a second fuel channel pressure mbe support pad spacer which functions as a spacer therebetween forming second fiiel channel pressure mbe support pad openings 113F. The second fiiel channel pressure mbe support pad 113 is interspersed throughout its length with The second fiiel channel pressure mbe support pad grooves 113E. The second fuel channel pressure tube support pad groove 113E and the second fuel channel pressure tube support pad openings 113F function for circulation of fluid.

Referring now to FIGURE 6 and FIGURE 6A which is a perspective view of an assembled and unassembled, respectively, of a fuel bundle 40 comprising: first fuel bundle proximal end plate 40AA; first fuel bundle proximal end plate fuel element end fastener 40AAA; first fuel bundle proximal end plate port 40AAB; first fuel bundle proximal end plate indent 40AAC; first fuel bundle proximal end plate opening 40AAD; second fiiel bundle distal end plate 40BA; second fuel bundle distal end plate fiiel element end fastener 40BAA; second fiiel bundle distal end plate port 40BAB; second fiiel bundle distal end plate indent 40BAC; second fiiel bundle distal end plate opening 40BAD; fuel element 40C; fuel bundle support 40D; fuel bundle support proximal end 40DA; fiiel bundle support proximal end spacer 40DB; fuel bundle support distal end 40DC; fuel bundle support distal end spacer 40DD; fuel bundle support spacer mbe 40DE; and fuel bundle support rod 40DF.

The second fiiel bundle distal end plate 40BA has a plurality of second fuel bundle distal end plate fuel element end fastener 40B AA which affix a second distal end of fuel elements 40C. The second fiiel bundle distal end plate 40B A has a plurality of second fuel bundle distal end plate port 40BAB interspersed throughout and between the second fuel bundle distal end plate fuel element end fasteners 40BAA. The second fuel bundle distal end plate indent 40BAC functions to accept the fuel bundle support nut 40DG therein. The second fuel bundle distal end plate opening 40BAD accepts the fuel bundle support distal end 40DC therethrough.

The fuel bundle support 40D has a fuel bundle support proximal end 40DA which passes through first fuel bundle proximal end plate opening 40AAD being secured by fuel bundle support nut 40DG. The fuel bundle support proximal end spacer 40DB functions to form a space between the fiiel bundle support 40D and the first fuel bundle proximal end plate 40AA. The fiiel bundle support distal end 40DC passes through second fuel bundle proximal end plate opening 40BAD being secured by fuel bundle support nut 40DG. The fiiel bundle support distal end spacer 40DD functions to form a space between the fiiel bundle support 40D and the second fuel bundle proximal end plate 40B A.

Now referring to FIGURE 6B which is a perspective view of a first fuel bundle end plate 40AA. Observe the plurality of first fuel bundle proximal end plate ports 40AAB interspersed throughout which function to increase circulation of fluid throughout the fiiel bundle 40. The first fuel bundle proximal end plate indent 40AAC is positioned on an exterior of the first fuel bundle proximal end plate opening 40AAD. The first fuel bundle proximal end plate indent 40AAC functions to accept the fuel bundle support nut 40DG therein. The first fuel bundle proximal end plate opening 40AAD accepts the fuel bundle support distal end 40DC therethrough. Referring to FIGURE 6C which is a perspective view of a fuel bundle support 40D. The fiiel bundle support 40D is composed of a fuel bundle support spacer mbe 40DE surrounding and encasing a fiiel bundle support rod 40DF. The function of this configuration is to increase strength, heating and cooling characteristics.

Referring to FIGURE 6D which is a cross-sectional view of a first fuel bundle end plate 40AA. Notice how the first fiiel bundle proximal end plate 40AA comprises a plurality of first fuel bundle proximal end plate fuel element end fasteners 40AAA which affix to a first distal end of a fuel ebment 40C. The first fuel bundle proximal end plate 40AA has multiple first fuel bundle proximal end plate ports 40AAB throughout which function to increase circulation of fluid throughout the fuel bundle 40. The first fuel bundle proximal end plate indent 40AAC is positioned on an exterior of the first fuel bundle proximal end plate opening 40AAD. The first fuel bundle proximal end plate indent 40AAC functions to accept the fiiel bundle support nut 40DG therein. The first fuel bundle proximal end plate opening 40AAD accepts the fuel bundle support distal end 40DC therethrough.

Referring to FIGURE 6E which is a cross-sectional view of a second fuel bundle end plate 40BA. The second fuel bundle distal end plate 40BA has a plurality of second fuel bundle distal end plate fiiel element end -fastener 40B AA which affix a second distal end of fuel elements 40C. The second fiiel bundle distal end plate indent 40BAC functions to accept the fuel bundle support nut 40DG therein. The second fiiel bundle distal end plate opening 40BAD accepts the fuel bundle support distal end 40DC therethrough.

Referring now to FIGURE 7 which is a cross-sectional view of a fuel channel pressure tube 14 having fiiel channel pressure mbe coating 14A; fiiel channel pressure tube lining 14B; and fuel channel pressure mbe cladding 14C which function to resist abrasion and increase inherent overall strength of the fuel channel pressure tube 14.

Refeiring to FIGURE 8 which is a cross-sectional view of a calandria mbe having coating, lining and cladding ofthe surfaces having calandria mbe coating 12A; calandria mbe lining 12B; and calandria tube cladding 12C which function to resist abrasion and increase inherent overall strength of the calandria tube 12.

Referring to FIGURE 9 is a cross-sectional view of a horizontal interior support pad 22 having horizontal interior support pad coating 22E, horizontal interior support pad lining 22F and horizontal interior support pad cladding 22G of the surfaces. Lastly, referring to FIGURE 10 which is a cross-sectional view of a refueling of a miniaturized reactor 10. The fuel channel pressure tube 14 has a joint connection at the end walls of the reactor for refilling. The joint connection is comprised of a joiner 48 having joiner thread 48A which screws into closure ring thread 50A being affixed to closure ring 50. The closure ring 50 is affixed to service mbe 52 which is connected to the fluids which circulate through the reactor 10.

Firstly, referring to FIGURE 11, which is a cross sectional view ofthe new stmctural member and pressure mbes exhibiting the following features: interior tube cavity 211 of the Calandria mbe 214; new stmctural member mbes 212 used as beam designed to support loads and stresses with minimal deflection ofthe Calandria tube 114 and fuel channel pressure mbe 218; Calandria tube 214 surrounding the fiiel channel pressure mbe 218 for support and stmctural strength; cylindrical air space 215 allowing flexible movement of the fuel channel pressure tube 218 within the Calandria mbe 214; support pads 216 to support and cushion the fuel channel pressure mbe 218 within the Calandria mbe 214; support pad 216A supporting the bottom of the fuel channel pressure mbe 218 within the Calandria mbe 214; intermediate bracing pad 216B supporting the side walls of the fiiel chaimel pressure mbe 218 within the Calandria mbe 214; fuel channel pressure mbe 218 inside ofthe Calandria mbe 214 holding the nuclear fuel for the reactor, steel plate or web 222 between two fuel channel pressure mbes 218 to give support and flexible strength to the fuel channel pressure mbes 218 surrounding the Calandria mbes 214; strap with bolt 224 attaching the Calandria mbes 214 to the steel plate or web 222.

Now, referring to FIGURE 12 which is a cross sectional view of the new structural member and pressure tubes along with a side view of the pressure tubes and web exhibiting the following features: interior tube cavity 211 of the Calandria mbe 214; new stmctural member tubes2 12 used as beam designed to support loads and stresses with minimal deflection of the Calandria mbe 214 and fuel channel pressure mbe 218; Calandria mbe 214 surrounding the fiiel channel pressure tube 218 for support and stmctural strength; cylindrical air space 215 allowing flexible movement of the fiiel channel pressure mbe 218 within the Calandria mbe 214; fuel channel pressure mbe 218 inside ofthe Calandria tube 214 holding the nuclear fuel for the reactor, steel plate or web 222 between two fuel channel pressure mbes 218 to give support and flexible strength to the fiiel channel pressure tubes 218 surrounding the Calandria mbes 214; steel plate or web support pad 222A supporting the upper fuel channel pressure mbes 218 within the new stmctural member mbes 212 restricting vertical movement of the fuel channel pressure tubes 218 as part of the steel plate or web 222; holes in steel plate or web 222C allows flexibility of the Calandria mbes 214.

Now, referring to FIGURE 13, which is a cross sectional view of the new stmctural members inside of the nuclear reactor exhibiting the following features: interior mbe cavity 211 of the Calandria tube 214; new stmctural member mbes 212 used as beam designed to support loads and stresses with minimal deflection of the Calandria mbe 214 and fuel channel pressure mbe 218; Calandria mbe 214 su-rrounding the fiiel channel pressure tube 218 for support and stmctural strength; cylindrical air space 215 allowing flexible movement of the fuel channel pressure tube 218 within the Calandria mbe 214; fiiel channel pressure mbe 218 inside of the Calandria tube 214 holding the nuclear fuel for the reactor, steel plate or web 222 between two fiiel channel pressure tubes 218 to give support and flexible strength to the fuel channel pressure tubes 218 suirounding the Calandria mbes 214; steel plate or web support pad 222A supporting the upper fuel channel pressure tubes 218 within the new stmctural member tubes 212 restricting vertical movement of the fuel channel pressure tubes 218 as part of the steel plate or web 222.

Now, refeπing to FIGURE 14, which is a second cross sectional view of the new stmctural members inside of the nuclear reactor exhibiting the following features: interior mbe cavity 211 of the Calandria mbe 214; new stmctural member mbes 212 used as beam designed to support bads and stresses with minimal deflection ofthe Calandria mbe 214 and fuel channel pressure mbe 218; Calandria mbe 214 surrounding the fuel channel pressure mbe 218 for support and stmctural strength; cylindrical air space 215 allowing flexible movement ofthe fuel channel pressure tube 218 within the Calandria tube 214; fuel channel pressure tube 218 inside of the Calandria tube 214 holding the nuclear fuel for the reactor; steel plate or web 222 between two fuel channel pressure tubes 218 to give support and flexible strength to the fuel channel pressure mbes 218 suirounding the Calandria mbes 214; steel plate or web support pad 222A supporting the upper fuel channel pressure mbes 218 within the new stmctural member mbes 212 restricting vertical movement of the fuel channel pressure mbes 218 as pan of the steel plate or web 222.

Now, referring to FIGURE 15, which is a cross sectional view of the new stmctural member and pressure mbes showmg the side bolts exhibiting the following features: interior tube cavity 211 of the Calandria tube 214; new stmctural member mbes 212 used as beam designed to support bads and stresses with minimal deflection ofthe Calandria mbe 214 and fuel channel pressure mbe 218; Calandria tube 214 suirounding the fuel channel pressure mbe 218 for support and stmctural strength; cylindrical air space 215 allowing flexible movement of the fuel channel pressure tube 218 within the Calandria mbe 214; fiiel channel pressure mbe 218 inside of the Calandria mbe 214 holding the nuclear fuel for the reactor, steel plate or web 222 between two fiiel channel pressure mbes 218 to give support and flexible strength to the fuel channel pressure mbes 218 surrounding the Calandria mbes 214; steel plate or web support pad 222A supporting the upper fuel channel pressure mbes 218 within the new stmctural member tubes 212 restricting vertical movement of the fuel channel pressure mbes 218 as part of the steel plate or web 222; steel plate or web bolts 222B attaching the Calandria mbes 214 to the steel plate or web 222.

Now, referring to FIGURE 16, which is a cross sectional view of the new stmctural members showing four pressure tube stmcture exhibiting the following features: fuel channel pressure mbe 218 inside of the Calandria mbe 214 holding the nuclear fuel for the reactor, four pressure tube stmctural member 220 holding four fuel channel pressure tubes 218 within the Calandria tubes 214.

Now, referring to FIGURE 17, which is a cross sectional view of the new stmctural members with various detail showing four pressure mbe stmcture with support details exhibiting the following features: fuel channel pressure mbe 218 inside of the Calandria mbe 214 holding the nuclear fuel for the reactor, four pressure mbe stmctural member 220 holding four fuel channel pressure mbes 218 within the Calandria tubes 214.

Now, referring to FIGURE 17A, which is a detail view of the center wall horizontal support inside ofthe cross sectional view ofthe new stmctural members with four pressure mbe stmcture exhibiting the folbwing features: four pressure mbe stmctural member 220 holding four fuel channel pressure mbes 218 within the Calandria mbes 214; four pressure tube stmctural member center wall horizontal support 220A supporting the upper fuel channel pressure mbe 218 and the lower fuel channel pressure tube 218 within the four pressure mbe stmctural member 220 restricting vertical movement of the fuel channel pressure mbes 218.

Now, referring to FIGURE 17B, which is a detail view of the center wall vertical support inside ofthe cross sectional view ofthe new stmctural members with four pressure mbe stmcture exhibiting the following features: four pressure mbe stmctural member 220 holding four fuel channel pressure mbes 218 within the Calandria mbes 214; four pressure mbe stmctural member center wall vertical support 220B supporting the left fuel channel pressure tube 218 and the right fiiel channel pressure mbe 218 within the four pressure mbe stmctural member 220 restricting horizontal movement ofthe fuel. Now, referring to FIGURE 17C, which is a detail view of the center wall comer support inside ofthe cross sectional view ofthe new stmctural members with four pressure mbe stmcture exhibiting the following features: four pressure mbe stmctural member 220 holding four fuel channel pressure mbes 218 within the Calandria tubes 214; four pressure tube stmctural member comer support 220C supporting the each ofthe fuel channel pressure mbes 218 within the four pressure mbe stmctural member 220 restricting rotational movement of the fuel channel pressure mbes 218; four pressure tube stmctural member comer support brace 220D supporting the four pressure tube stmctural member co er support 220C in order to support the fiiel channel pressure tubes 218.

Lastly, referring to FIGURE 17D, which is a detail view of the center wall bottom support inside ofthe cross sectional view ofthe new structural members with four pressure tube structure exhibiting the following features: four pressure tube stmctural member 220 holding four fuel channel pressure mbes 218 within the Calandria mbes 214; four pressure tube stmctural member comer support brace 220D supporting the four pressure tube stmctural member comer support 220C in order to support the fuel channel pressure tubes 218.

It will be understood that each ofthe elements described above, or two or more together, may also find a useful application in other types of constmctions differing from the type described above.

While the invention has been illustrated and described as embodied in a stmctural member for nuclear reactor pressure tubes, it is not intended to be limited to the details shown, since it will be understood that various omissions, modifications, substimtions and changes in the forms and details ofthe device illustrated and in its operation can be made by those skilled in the art without departing in any way from the spirit of the present invention.

Without further analysis, the foregoing wui so fully reveal the gist of the present invention that others can, by applying current knowledge, readily adapt it for various applications without omitting features that, from the standpoint of prior art, fairly constitute essential characteristics of the generic or specific aspects of this invention.

What is claimed as new and desired to be protected by Letters Patent is set forth in the appended claims.

Claims

I Claim:

1. A miniaturized nuclear reactor utilizing improved pressure mbe stmctural members comprising:

a) a moderator (20) having: a top reactor wall, a bottom reactor wall, a reactor front wall, a reactor back wall, and two reactor side walls : b) at least one calandria mbe (12) contained within the moderator (20); c) at least one fuel channel pressure mbe (14) contained within the at least one calandria mbe (12); d) at least one fuel bundle (26) contained within the at least one fuel channel pressure tube (14) e) at least one fuel channel pressure mbe pad (18) positioned between the at least one calandria tube (12) and the at least one fuel channel pressure tube (14); f) at least one horizontal exterior support pad (30) positioned on the bottom reactor wall, the at least one horizontal exterior support pad (30) is positioned between the at least one calandria mbe (12) and the bottom reactor wall; g) at least one fuel bundle support pad (16) positioned between the at least one fiiel bundle (26) and the at least one fuel channel pressure tube (14); h) at least one vertical support pad (24) positioned on a reactor side wall between the at least one calandria tube (12) and the reactor side wall; I) at least one angular support pad (28) positioned on a comer formed between the reactor top wall and the reactor side wall, the at least one angular support pad (28) extending angularly from the comer, the at least one angular support pad functioning to maintain a space between the at least one calandria mbe (12) and the reactor top and side walls; j) at least one moderator system comprises: at least one moderator inlet, at least one moderator outlet, at least one moderator pump, and at least one moderator cooler, k) at least one coolant system which comprises: at least one coolant inlet, at least one coolant outlet, and at least one coolant gas fan; 1) at least one heat exchanger system which comprises: at least one inlet, at least one outlet, at least one turbine, at least one generator, at least one condenser, and at least one feed water pump.

2. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the moderator (20) further comprises:

a) a moderator (20) having: a top reactor wall, a bottom reactor wall, a reactor front wall, a reactor back wall, two reactor side walls, and a reactor horizontal interior wall; b) a pair of calandria mbes (12) being an upper calandria mbe and a lower calandria tube contained within the moderator (20); c) a pair of fuel chaimel pressure tubes (14) being an upper fuel channel pressure mbe contained within the upper calandria tube and a lower channel pressure tube contained within the lower calandria tube; d) a pair of fuel bundles (26) being an upper fuel bundle contained within the upper fuel chaimel pressure tube and a lower fuel bundle contained within the lower fuel channel pressure mbe; e) at least two fuel channel pressure tube pads (18) being an upper fuel channel pressure tube pad positioned between the upper calandria mbe and the upper fuel channel pressure mbe and a lower fuel channel pressure mbe pad positioned between the lower calandria mbe and the lower fuel channel pressure tube. f) at least one horizontal exterior support pad (30) positioned on the bottom reactor wall, the at least one horizontal exterior support pad (30) is positioned between the lower calandria tube and the bottom reactor wall; g) at least two fuel bundle support pads (16) being an upper fuel bundle support pad positioned between the upper fuel bundle and the upper fuel channel pressure mbe and a lower fuel bundle support pad positioned between the lower fuel bundle and the lower fuel channel pressure mbe; h) at least two vertical support pads (24) being an upper vertical support pad positioned on an upper reactor side wall between the upper calandria mbe and the upper reactor side wall and a bwer vertical support pad positioned on a bwer reactor side wall between the lower calandria mbe and the lower reactor side wall;

I) at least two angular support pads (28) being an upper angular support pad positioned on a comer formed between the reactor top wall and the reactor side wall, the upper angular support pad extending angularly from the comer and a lower angular support pad positioned on a comer formed between the reactor bottom wall and the reactor side wall, the lower angular support pad extending angularly from the comer, the upper angular support pad functioning to maintain a space between the upper calandria mbe and the reactor top and side walls, the lower angular support pad functioning to maintain a space between the lower calandria mbe and the reactor bottom and side walls; j) at least one horizontal interior support pad (22) positioned between an upper calandria mbe and the at least one reactor horizontal interior wall; k) at least one moderator system comprises: at least one moderator inlet, at least one moderator outlet, at least one moderator pump, and at least one moderator cooler, 1) at least one coolant system which comprises: at least one coolant inlet, at least one coolant outlet, and at least one coolant gas fan; m) at least one heat exchanger system which comprises: at least one inlet, at least one outlet, at least one turbine, at least one generator, at least one condenser, and at least one feed water pump.

3. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the calandria mbe (12) further comprises: a calandria mbe coating (12A); a calandria tube lining (12B); and a calandria mbe cladding 12C.

4. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the fuel channel pressure mbe (14) further comprises: a fuel channel pressure mbe coating (14A); a fiiel channel pressure mbe lining (14B); and a fuel channel pressure tube cladding (14C).

5. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the fiiel bundle (16) further comprises a pair of fuel bundle support pad spacers (16A) positioned at opposite distal ends of a fuel bundle support pad strap (16B).

6. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the fuel channel pressure mbe pad further comprises a pair of fuel channel pressure mbe pad vertical spacer (18 A) which is at an obmse angle to each of a pair of fuel channel pressure mbe pad ends (18B), a fuel channel pressure mbe pad horizontal spacer (18C) connected at opposite distal ends to each one of the fuel channel pressure mbe pad vertical spacers (18A).

7. The n- niaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 2, wherein the horizontal interior support pad further comprises: a horizontal interior support pad proximal end (22A), a horizontal interior support pad distal end (22B), a horizontal interior support pad groove (22C), and a horizontal interior support pad concave (22D), the horizontal interior support pad groove (22C) fitting snugly around a reactor horizontal interior wall, the horizontal interior support pad concave (22D) functioning as a cradle upon which the upper calandria tube rests upon.

8. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 7, wherein the horizontal interior support pad further comprises: a horizontal interior support pad coating (22E), a horizontal interior support pad lining (22F), and a horizontal interior support pad cladding (22G).

9. The miniaturized nuclear reactor utilizing improved pressure mbe structural members as described in claim 1, wherein the angular support pad (28) further comprises: an angular support pad top member (28A) and an angular support pad bottom member (28B), the angular support pad top member (28 A) abutting the calandria mbe (12), and the angular support pad bottom member (28B) securely fastened to the comer.

10. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the horizontal exterior support pad (30) further comprises a horizontal exterior support pad end (30A), a horizontal exterior support pad fastener (30B), and a horizontal exterior support pad concave (30C), the horizontal exterior support pad fastener (30B) securely affixes the horizontal exterior support pad (30) to the reactor bottom wall, and the horizontal exterior support pad concave (30C) functioning as a cradle within which the calandria tube (12) rests.

11. The miniaturized nuclear reactor utilizing improved pressure tube stmctural members as described in claim 1, wherein the fuel bundle (40) further comprises:

a) a first fuel bundle proximal end plate (40AA) having a plurality of first fuel bundle proximal end late fiiel element end fasteners (40AAA), further having a plurahty of first fuel bundle proximal end plate port (40AAB), still further having a first fuel bundle proximal end plate indent (40AAC), yet still further having a first fuel bundle proximal end plate opening (40AAD);

b) a second fiiel bundle distal end plate (40BA) having a plurahty of second fuel bundle distal end plate fuel element end fasteners (40BAA), a plurahty of second fuel bundle distal end plate ports (40BAB), a second fiiel bundle distal end plate indent (40BAC) and a second fuel bundle distal end plate opening (40BAD);

c) a fuel bundle support (40D) having a fuel bundle support proximal end (40DA), a fuel bundle support proximal end spacer (40DB), a fuel bundle support distal end (40DC), a fuel bundle support distal end spacer (40DD), a fuel bundle support spacer tube (40DE), a fuel bundle support rod 40DF, and a fuel bundle support nut 40DG; and

d) a plurahty of fuel elements (40C) each having a proximal and distal end, the proximal end of each fuel element (40C) affixed within each of the first fuel bundle proximal end plate fuel element end fasteners (40AAA) and the distal end of each fuel element (40C) affixed within each of the second fuel bundle distal end plate fuel element end fasteners (40B AA).

12. The miniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the moderator (20) further comprises:

a) a moderator (20) having: a left top reactor wall, a right top reactor wall, a bottom left reactor wall, a bottom right reactor wall, a reactor front wall, a reactor back wall, a reactor upper left exterior side wall, a reactor lower left exterior side wall, a reactor upper right exterior side wall, a reactor lower right exterior side wall, at least one reactor horizontal interior wall having a reactor horizontal interior left and right wall, and at least one reactor vertical interior wall having a reactor vertical interior upper and lower wall, the moderator (20) thereby being divided into at least four compartments being an upper left compartment, an upper right compartment, a lower left compartment, and a lower right compartment, the upper left compartment being bordered at the bottom by a reactor left horizontal interior wall and a reactor upper vertical interior wall and a reactor upper left exterior side wall and a reactor left top wall, the upper right compartment being bordered at the bottom by a reactor right horizontal interior wall and a reactor upper vertical interior wall and a reactor upper right exterior side wall and a reactor upper right top wall, the lower left compartment being bordered at the bottom by a reactor left bottom wall and a reactor left horizontal interior wall and a reactor bwer vertical interior wall and a reactor lower left exterior side wall and a reactor left bottom wall, the lower right compartment being bordered at the bottom by a reactor right bottom wall and a reactor right horizontal interior wall and a reactor lower right exterior side wall and a reactor right bottom wall;

b) at least four calandria mbes (12) being an upper left calandria mbe, upper right calandria mbe, a lower left calandria mbe, and a lower right calandria mbe contained within the upper left, upper right, lower left, and lower right compartments, respectively, of the moderator (20);

c) at least four fuel channel pressure mbes (14) each fuel channel pressure mbe contained within each of the calandria mbes;

d) at least four fuel bundles (26) each fuel bundle contained within each of the fiiel channel pressure mbes;

e) at least four fuel channel pressure tube pads (18) each fuel chaimel pressure mbe pad positioned between each of the calandria mbes and each of the fiiel channel pressure mbes;

f) at least two horizontal exterior support pad (30), one horizontal exterior support pad positioned on the left bottom reactor wall and the other horizontal exterior support pad positioned on the right bottom reactor wall, the horizontal exterior support pads (30) are positioned between the lower left and lower right calandria mbes and the bottom left and bottom right reactor walls, respectively; g) at least four fuel bundle support pads (16) being each bundle support pad positioned between each of the fuel bundles and each of the fuel channel pressure tubes;

h) at least two vertical support pads (24) being an upper vertical support pad positioned on an upper reactor vertical interior wall between the upper left and upper right calandria mbes and a bwer vertical support pad positioned on a bwer reactor side wall between the lower left and lower right calandria mbes;

i) at least four angular support pads (28) being an upper left angular support pad positioned on a comer formed between the reactor left top wall and the reactor upper left exterior side wall, the upper left angular support pad extending angularly from the comer and an upper right angular support pad positioned on a comer formed between the reactor right top wall and the reactor upper right exterior side wall, the upper right angular support pad extending angularly from the comer, and a lower left angular support pad positioned on a comer formed between the reactor left bottom wall and the reactor lower left exterior side wall, the lower left angular support pad extending angularly from the comer, and a lower right angular support pad positioned on a comer formed between the reactor right bottom wall and the reactor lower right exterior side wall, the lower right angular support pad extending angularly from the comer, the angular support pads functioning to maintain a space between the calandria tube and the reactor walls;

j) at least two horizontal interior support pad (22), one horizontal interior support pad positioned within the left reactor horizontal interior wall and the other horizontal interior support pad positioned within the right reactor horizontal interior wall, the left horizontal interior support pad functioning to maintain a space between the upper left and lower left calandria mbes, and right horizontal interior support pad functioning to maintain a space between the upper right and lower right calandria mbes;

k) at least one moderator system comprises: at least one moderator inlet, at least one moderator outlet, at least one moderator pump, and at least one moderator cooler, 1) at least one coolant system which comprises: at least one coolant inlet, at least one coolant outlet and at least one coolant gas fan; and

m) at least one heat exchanger system which comprises: at least one inlet, at least one outlet, at least one turbine, at least one generator, at least one condenser, and at least one feed water pump.

13. The imitiaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 12, wherein the vertical support pad (24) further comprises at least two vertical support pads (24) being an upper vertical support pad and a lower vertical support pad, The upper and lower vertical support pads securely affixed within the reactor upper interior vertical wall and the reactor bwer interior wall, respectively, each ofthe vertical support pads (24) having a vertical support pad proximal end (24A), a vertical support pad distal end (24B), a vertical support pad groove (24C), and a vertical support pad concave (24D), the vertical support pad groove (24C) fitting snugly around a upper reactor vertical interior wall and a lower reactor vertical interior wall, respectively, the vertical support pad concave (24D) ofthe upper vertical support pad functioning as a cradle upon which the interior sides of the upper left calandria tube and the upper right calandria mbe rests upon, the lower vertical support pad functioning as a cradle upon which the interior sides of the lower left calandria tube and the lower right calandria mbe rests upon.

14. The rniniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 1, wherein the reactor further comprises: a least one joint connector (48) having a joint connector tread (48A), a joiner ring (50) with a joiner ring thread (50), the joint connector tread (48A) connects to the joiner ring thread (50) and a service tube (52) connected to the joiner ring (50) functioning for refueling of the reactor.

15. The π-dniaturized nuclear reactor utilizing improved pressure mbe stmctural members as described in claim 2, wherein the calandria tubes further comprise a fuel compartment pressure mbe (17) therebetween.

16. a miniaturized nuclear reactor utilizing improved pressure mbe stmctural members comprising:

a) a moderator (20) having: a top reactor wall, a bottom reactor wall, a reactor front wall, a reactor back wall, and two reactor side walls :

b) at least one second calandria mbe (112) having a plurahty of second calandria mbe compartments (112A) securely affixed around an inside perimeter contained within the moderator (20);

c) at bast one second fuel channel pressure tube (114) having a plurahty of second fuel channel pressure tube conφartment (114A) securely affixed around an outside perimeter, the plurahty of second calandria tube compartments (112A) and the plurahty of second fiiel channel pressure mbe compartment (114A) opposing each other in an interlocking configuration, the at least one second fiiel channel pressure mbe (114) contained within the at least one second calandria mbe (112);

d) at least one fuel bundle (26) contained within the at least one second fuel channel pressure mbe (114);

e) at least one second f iel channel pressure mbe support pad (113) having a second fuel chaimel pressure mbe support pad end (113A), a second fiiel channel pressure mbe support pad spacer (113B), a second fuel chaimel pressure mbe suppon pad concave (113C), a second fuel channel pressure mbe support pad convex (113D), a second fuel channel pressure tube support pad groove (113E), and a second fiiel channel pressure mbe support pad opening (113F) positioned between the at least one calandria mbe (12) and the at least one second fuel channel pressure mbe (114);

f) at least one horizontal exterior support pad (30) positioned on the bottom reactor wall, the at least one horizontal exterior support pad (30) is positioned between the at least one second calandria tube (112) and the bottom reactor wall; g) at least one fuel bundle support pad (16) positioned between the at least one fuel bundle (26) and the at least one fuel channel pressure tube (14);

h) at least one vertical support pad (24) positioned on a reactor side wall between the at least one calandria tube (12) and the reactor side wall;

i) at least one angular support pad (28) positioned on a comer formed between the reactor top wall and the reactor side wall, the at least one angular suppon pad (28) extending angularly from the comer, the at least one angular support pad functioning to maintain a space between the at least one calandria mbe (12) and the reactor top and side walls;

j) at least one moderator system comprises: at least one moderator inlet, at least one moderator outlet at least one moderator pump, and at least one moderator cooler;

k) at least one coolant system which comprises: at least one coolant inlet, at least one coolant outlet, and at least one coolant gas fan;

1) at least one heat exchanger system which comprises: at least one inlet, at least one outlet, at least one turbine, at least one generator, at least one condenser, and at least one feed water pump.

17.A stmctural member for nuclear reactor pressure tubes used as beam designed to support loads and stresses with minimal deflection of a Calandria tube, comprising:

a) an interior tube cavity of said Calandria mbe having fuel channel pressure mbe;

b) a cylindrical air space positioned circumventially betweeen said fuel channel pressure tube and said Calandria tube allowing flexible movement of said fuel channel pressure mbe within said Calandria mbe; c) a plurahty of support pads positioned between said fuel channel pressure mbe and said Calandria mbe, supporting and cushioning said fiiel channel pressure tube within said Calandria mbe;

d) an intermediate bracing pad positioned said fiiel channel pressure mbe and said Calandria mbe supporting side walls of said fuel channel pressure mbe within said Calandria mbe;

e) a fuel channel pressure mbe positioned within an inner position of said Calandria mbe functioning to hold nuclear fuel;

f) a steel plate positioned between said plurality of said fuel channel pressure tubes supporting and conferring flexible strength to said fiiel channel pressure tubes suirounding said Calandria mbes; and

g) a web support pad positioned between adjacent Calandria mbes supporting said upper fuel channel pressure mbes within said stmctural member mbes restricting vertical movement of said fuel channel pressure mbes being part of said steel plate.

18. A stmctural member for nuclear reactor pressure mbes being utihzed as beams designed supporting loads and stresses with minimal deflection of said Calandria mbe, comprising:

a) a multiple pressure mbe stmctural member holding a plurahty of fuel chaimel pressure mbes within said Calandria mbes;

b) a center wall horizontal support supporting an upper fuel channel pressure mbe and a lower fuel channel pressure mbe within said plurahty of pressure mbe stmctural members restricting vertical movement of said fuel channel pressure mbes;

c) a center wall vertical support supporting a first fuel channel pressure mbe and a second fuel channel pressure mbe within said plurahty of pressure mbe stmctural members restricting horizontal movement of said fuel channel pressure mbes; d) a comer support supporting each of said fuel channel pressure mbes within said plurahty of pressure mbe stmctural members restricting rotational movement of said fuel channel pressure tubes; and

e) a bottom support supporting a lower fuel channel pressure mbes within said plurahty of pressure mbe stmctural member restricting vertical movement of said fuel channel pressure mbes.

19. The stmctural member for nuclear reactor pressure tubes as described in claim 2, whereas said Calandria tubes having plurahty of bolts attaching said Calandria tubes to said steel plate.

20. The stmctural member for nuclear reactor pressure tubes as described in claim 3, whereas said steel plate having holes allowing flexibility of said Calandria tubes.

21.The stmctural member for nuclear reactor pressure mbes as described in claim 1 , whereas said stmctural member for nuclear reactor pressure tube being composed of a group of materials individuaUy and in combination such as metal, metal alloys, ceramic, plastic plastic composites, petroleum derivitives, epoxy, carbon-graphite, fiberglass, stone, and cement