Underground nuclear power station using self-regulating heat-pipe controlled reactors

• US 4,851,183 A
• Filed: 05/17/1988
• Issued: 07/25/1989
• Est. Priority Date: 05/17/1988
• Status: Expired due to Fees

• Current Assignee: United States Department of Energy
• Original Assignee: United States Department of Energy
• Inventors: Hampel, Viktor E.
• Primary Examiner(s): Kyle, Deborah L.
• Assistant Examiner(s): Wendtland, Richard W.
• Application Number:
  US07/194,772
• Time in Patent Office: 434 Days
• Field of Search: 376/272, 376/273, 376/274, 376/275, 376/276, 376/367, 376/911, 376/914
• US Class Current: 376/274
• CPC Class Codes: F28D 15/00 Heat-exchange apparatus with the intermediate heat-transfer medium in closed tubes passing into or through the conduit walls ; Heat-exchange apparatus employing intermediate heat-transfer medium or bodies F28D17/00, F28D19/00, F28D20/00 take precedence
• CPC Class Codes: F28D 15/0275 Arrangements for coupling heat-pipes together or with other structures, e.g. with base blocks; Heat pipe cores
• CPC Class Codes: F28D 15/06 Control arrangements therefor
• CPC Class Codes: F28D 2021/0054 for nuclear applications cooling arrangements for nuclear reactors G21C15/00
• CPC Class Codes: G21C 11/06 Reflecting shields, i.e. for minimising loss of neutrons
• CPC Class Codes: G21C 13/00 Pressure vessels; Containment vessels; Containment in general for chemical or physical processes B01J3/00; pressure vessels in general F16J12/00
• CPC Class Codes: G21C 15/257 using heat-pipes in general F28D, F28F
• CPC Class Codes: G21C 7/26 by displacement of the moderator or parts thereof by changing the moderator concentration
• CPC Class Codes: G21C 7/28 by displacement of the reflector or parts thereof
• CPC Class Codes: G21C 9/02 Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergencycontrol elements per se G21C7/00
• CPC Class Codes: G21D 1/00 Details of nuclear power plant control G21D3/00
• CPC Class Codes: Y02E 30/00 Energy generation of nuclear origin
• CPC Class Codes: Y02E 30/30 Nuclear fission reactors
• CPC Class Codes: Y10S 376/911 Plural reactor systems

Abstract

A nuclear reactor for generating electricity is disposed underground at the bottom of a vertical hole that can be drilled using conventional drilling technology. The primary coolant of the reactor core is the working fluid in a plurality of thermodynamically coupled heat pipes emplaced in the hole between the heat source at the bottom of the hole and heat exchange means near the surface of the earth. Additionally, the primary coolant (consisting of the working flud in the heat pipes in the reactor core) moderates neutrons and regulates their reactivity, thus keeping the power of the reactor substantially constant. At the end of its useful life, the reactor core may be abandoned in place. Isolation from the atmosphere in case of accident or for abandonment is provided by the operation of explosive closures and mechanical valves emplaced along the hole. This invention combines technology developed and tested for small, highly efficient, space-based nuclear electric power plants with the technology of fast-acting closure mechanisms developed and used for underground testing of nuclear weapons. This invention provides a nuclear power installation which is safe from the worst conceivable reactor accident, namely, the explosion of a nuclear weapon near the ground surface of a nuclear power reactor.

Claims

1. A nuclear power generating facility, comprising:

a substantially vertical borehole in the surface of the earth which is at least 600 feet deep and has a substantially constant diameter;

a casing, extending from the surface of the earth down to at least 600 feet deep, lining the borehole and wherein the casing is completely within the borehole;

a self regulating nuclear reactor, of a diameter less than the diameter of the borehole, within the casing at least 600 feet below the surface of the earth, wherein the reactor generates heat;

means for converting the heat generated by the reactor to electricity, wherein the conversion means is located at or above the surface of the earth;

means for transferring the heat generated by the reactor from the reactor to the conversion means; and

a means for completely and permanently closing all access between the surface of the earth and the reactor through the borehole, wherein said means is located between the reactor and the surface of the earth, and wherein the casing and the borehole have no opening below the closing means sealing the reactor within the casing.

2. A nuclear power generating facility, as cited in claim 1, wherein the means for completely and permanently closing access is able to completely close access in less than 0.5 seconds after actuation to prevent the accidental upward movement of radioactive materials within the casing after actuation.

3. A nuclear power generating facility, as cited in claim 2, wherein the means for completely and permanently closing access comprises gas driven doors which move from a fully open to fully closed positions in less than or equal to substantially 40 milliseconds against a pressure differential as high as substantially 1600 psi to prevent the accidental upward movement of radioactive materials within the casing after actuation.

4. A nuclear power generating facility, as cited in claim 2, wherein the means for completely and permanently closing access, comprises:

a first acting, high explosive actuated pipe closure; and

a plurality of later acting mechanical valves located between the first acting closure and the surface of the earth.

5. A nuclear power generating facility, as cited in claim 1, wherein the means for transferring the heat comprises a heat pipe array.

6. A nuclear power generating facility, as cited in claim 5, wherein the heat pipe array comprises a plurality of thermally coupled heat pipe stages.

7. A nuclear power generating facility, as cited in claim 5, wherein the heat pipe array comprises a first heat exchanger, and a first plurality of heat pipes, which have first ends which are located in the reactor and which have second ends which are located in the first heat exchanger.

8. A nuclear power generating facility, as cited in claim 7, wherein the first ends of the first plurality of heat pipes are conical with the apex of each cone located on the part of the first ends furthest from the second ends, and wherein the second ends of the first plurality of heat pipes are conical with the apex of each cone located on the part of the second ends furthest from the first ends, and wherein the second ends comprise semi-helical baffles.

9. A nuclear power generating facility, as cited in claim 8, wherein the heat pipe array further comprises, a second heat exchanger and a second plurality of heat pipes, which have first ends which are located in the first heat exchanger and second ends located in the second heat exchanger.

10. A nuclear power generating facility, as cited in claim 7, wherein the self regulating nuclear reactor is a self regulating heat pipe controlled nuclear reactor.

11. A nuclear power generating facility, as cited in claim 10, wherein the self regulating nuclear reactor is a self regulating heat pipe controlled, reflector critical nuclear reactor.

12. A nuclear power generating facility, as cited in claim 1, wherein the self regulating nuclear reactor is a fast breeder reactor.

13. A nuclear power generating facility, as cited in claim 1, wherein the diameter of the borehole is less than 6 meters.