US3854524A - Thermal switch-heat pipe - Google Patents

Thermal switch-heat pipe Download PDF

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Publication number
US3854524A
US3854524A US00287211A US28721172A US3854524A US 3854524 A US3854524 A US 3854524A US 00287211 A US00287211 A US 00287211A US 28721172 A US28721172 A US 28721172A US 3854524 A US3854524 A US 3854524A
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US
United States
Prior art keywords
defining
wall member
heat
temperature
heat pipe
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Expired - Lifetime
Application number
US00287211A
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English (en)
Inventor
K Gregorie
H Pfefferlen
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US Atomic Energy Commission (AEC)
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US Atomic Energy Commission (AEC)
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Filing date
Publication date
Application filed by US Atomic Energy Commission (AEC) filed Critical US Atomic Energy Commission (AEC)
Priority to US00287211A priority Critical patent/US3854524A/en
Priority to GB3819573A priority patent/GB1388977A/en
Priority to DE19732341757 priority patent/DE2341757A1/de
Priority to FR7332390A priority patent/FR2199103B3/fr
Priority to JP48101025A priority patent/JPS4968198A/ja
Application granted granted Critical
Publication of US3854524A publication Critical patent/US3854524A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

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Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D15/00—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
    • F28D15/02—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 in which the medium condenses and evaporates, e.g. heat pipes
    • F28D15/04—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 in which the medium condenses and evaporates, e.g. heat pipes with tubes having a capillary structure
    • F28D15/046—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 in which the medium condenses and evaporates, e.g. heat pipes with tubes having a capillary structure characterised by the material or the construction of the capillary structure
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/30—Subcritical reactors ; Experimental reactors other than swimming-pool reactors or zero-energy reactors
    • G21C1/303—Experimental or irradiation arrangements inside the reactor
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • a radial heat pipe is fitted with a wick and working fluid for the temperature of interest and operated in such a manner as to act as a thermal switch.
  • the heat pipe surrounds nuclear fuel elements and during normal temperature operation transports negligible energy but upon a surge in fuel element temperature large amounts of heat can be transported to limit the fuel element temperature.
  • This invention relates to safety systems for nuclear reactors, particularly to means for limiting the temperature of nuclear fuel due to loss of coolant, and more particularly to a type of thermal switch which transports negligible heat during normal operation but large amounts of heat during a temperature excursion.
  • the overall coolant system is similar to that of US. Pat. No. 3,525,669.
  • one of the major hazards to be considered in a long term nuclear fuel irradiation in a forced circulation sodium-cooled system is the consequence of loss of flow.
  • a power outage, pump failure, or flow blockage could each cause loss of sodium flow with possible overheating of the fuel elements unless there is some means of dissipating the heat in the vicinity of the fuel elements.
  • the present invention provides a means capable of causing a large change in the thermal conductivity of a double walled structure by a relatively small change in the temperature of the hotter side of the structure.
  • This is accomplished by a novel double wall structure which acts as an annular heat pipe.
  • the working fluid of the heat pipe is such that in the temperature range of interest radial heat transfer through the double wall will vary from negligible to large.
  • the heat pipe for example, being operated exclusively in the startup regime of a nuclear reactor.
  • the heat pipe is fitted with a wick and working fluid such that it acts as a thermal switch with negligible heat transported during normal operaity of a double walled structure by a relatively small change in the temperature of the hotter side of the double wall structure.
  • Another object is to provide a radial heat pipe containing a suitable wick and working fluid to transport negligible heat during normal operating temperatures but large amounts of heat during a temperature excur- SlOIl.
  • FIG. 1 schematically illustrates a forced sodium circulation nuclear fuel capsule utilizing the inventive heat pipe
  • FIG. 2 partially in cross-sectionpartially illustrates the inventive heat pipe positioned about a nuclear fuel element
  • FIG. 3 graphically illustrates the evaporation rate of lithium relative to increasing temperature
  • FIG. 4 graphically illustrates the heat transfer capabilities of various liner designs as a function of temperature
  • FIG. 5 graphically illustrates the performance of a sodium heat pipe thermal switch made in accordance with the invention for various condenser temperatures.
  • the invention is directed to a means capable of causing a large change in the thermal conductivity of a double walled structure by a relatively small change in the temperature of the hotter side of the structure, and is accomplished by a double wall structure which acts as an annular heat pipe.
  • the working fluid of the heat pipe is selected so that in the temperature range of interest radial heat transfer through the double wall structure will vary from negligible to large.
  • the invention is described and illustrated in an application for the transfer of large amounts of heat from fuel elements in a nuclear reactor during a temperature excursion while negligible heat is transferred during normal operation temperatures.
  • the invention is not limited to this specific application and may readily be utilized wherever a similar heat transfer need arises.
  • the invention generally comprises a radial heat pipe which is fitted with a suitable wick and working fluid for the temperature of interest and operated in such a manner as to act as a thermal switch.
  • FIG. 1 schematically illustrates a forced sodium circulation capsule utilized, for example, in irradiation tests of nuclear fuel pins or elements and comprises a primary containment 10, a secondary containment 11 positioned in spaced relationship within primary containment 10 so as to define a binary gas annulus l2 therebetween.
  • a plurality of fuel pins 13 are located within a casing 14 which is centrally positioned in spaced relationship within secondary containment 11, to define a space 15 therebetween, and abuts at the upper end thereof, through appropriate sealing means, with a pump assembly generally indicated at 16, space 15 serving as a downward flow channel for the sodium coolant discharged from pump assembly 16 as indicated by the arrows, with the upward coolant flow being within casing 14 around fuel pins 13 as indicated by the upward directed arrows thereby producing a forced sodium circulation loop.
  • a flow deflector 16' is mounted in pump assembly 16 to direct coolant discharge in a downward direction.
  • a liner 17 is positioned in spaced relation about casing 14 defining a chamber or annulus 18 therebetween. The lower end of casing 14 is provided with a reduced diameter portion 19 so as to accommodate the positioning of a flowmete'r 20 between the lower end of liner 17 and reduced diameter portion 19 of casing 14.
  • annulus l8 defined between casing 14 and liner 17 (hereinafter referred to as an unmodified liner) was filled with an insulating gas, such as neon or helium, thereby effectively inhibiting radial heat transfer through the liner 17.
  • an insulating gas such as neon or helium
  • FIG. 2 a portion of an embodiment of the invention is illustrated, which basically involves the modification of the casing-liner assembly (elements 14 and 17) of FIG. 1 to incorporate thereinto an annular heat pipe, and like elements to those of FIG. 1 will be given similar reference numerals.
  • casing 14 and liner 17' are interconnected by a member 21 thus defining a closed end annular chamber 22 about the fuel pins 13 (only one shown), the lower end of the annular chamber 22 constituting a reservoir 23 for lithium orother suitable material.
  • a wick 24 is secured to the inner surface of casing 14 and may, for example, consist of a layer of powdered stainless steel bonded thereto or several layers of fine mesh screen.
  • the structure 14, 17 and 21-24 defines an annular heat pipe wherein the casing 14 constitutes the evaporator thereof and liner 17' constitutes the condenser of the heat pipe, with lithium, for example, as the working fluid in reservoir 23 serving to replenish the wick 24.
  • Heat transfer (Q) is'indicated by the arrows across chamber 22.
  • the sodium coolant flow indicated by arrows 25 and 26 is circulated, for example, in the same manner as described above in FIG. 1. While not shown in FIG. 2, the flowmeter 20 or other desired instrumentation may be attached to the member 21 in a manner similar to FIG. 1.
  • Lithium as the working fluid in reservoir 23 has the following advantages:
  • High surface tension in the liquid phase (about 350 dynes/cm) enables the lithium to climb the full height of the wick (25 inches in this embodiment) via capillary action and maximizes wetting of the wick by the lithium.
  • High heat of vaporization (4680 cal/gm) increases the heat content of the lithium vapor effectively decreasing the response time of the heat pipe.
  • FIG. 4 summarizes the heat transfer capabilities of various heat pipe designs as a function of the temperature of the i.d., (evaporator) surface assuming an average temperature of 980F on the o.d., (condenser) surface.
  • the total radial heat transfer through the abovedescribed lithium heat pipe would be about 1 percent of the total heat generation of a fuel pin, thus not enough to effect the precision of sodium calorimetry.
  • the event of a temperature excursion in the upward flowing sodium see FIG.
  • FIG. 5 shows how the operation of a sodium, rather than lithium as the working medium in the inventive heat pipe thermal switch would be effected by different condenser temperatures.
  • response of the so dium heat pipe is slower" for higher condenser temperatures.
  • condenser temperature is increased, a greater evaporator temperature increase is required for a given increase in radial heat transfer capability.
  • the curves of FIG. 5 are normalized to the same starting point for convenience of comparison.
  • a lithium heat pipe would show the same general behavior as the sodium heat pipe since the shapes of their vapor pressure curves are essentially identical.
  • the present invention provides a means for causing a large change in the thermal conductivity of a double walled structure by a relatively small change in the temperature of the hotter side of the structure.
  • a means basically comprises a heat pipe which functions as a thermal switch and has particular application for requirements where the heat transfer through the double walled structure must vary from negligible to large, such an application being in nuclear fuel elements where negligible heat is to be transported during normal operating temperatures but large amounts of heat need be transported during a temperature excursion.
  • An apparatus defining a thermal switch positioned about a nuclear heat source capable of producing a large change in thermal conductivity of a structure by a relatively small change in the temperature of the hotter side of the structure such that negligible heat is transported during a predetermined operating temperature of the structure while a large amount of heat is transported during a temperature excursion comprising: vertically positioned annular evaporator means defining a first wall member, annular condenser means positioned externally of and in vertical spaced relationship with respect to said evaporator means and defining a second wall member, means defining a third member interconnecting one end of said wall member of said evaporator means and one end of said wall member of said condenser means defining an annular chamber therebetween and forming an annular reservoir for working fluid at the lower end portion thereof, wick means located within said chamber and said reservoir and secured only to said wall member of said evaporator means, said wick means being selected from the group consisting of a plurality of layers of fine mesh screen and a layer of powder
  • said heat source comprises a plurality of nuclear fuel pins wherein said first wall member surrounds said fuel pins defining a coolant flow path therebetween.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
US00287211A 1972-09-07 1972-09-07 Thermal switch-heat pipe Expired - Lifetime US3854524A (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
US00287211A US3854524A (en) 1972-09-07 1972-09-07 Thermal switch-heat pipe
GB3819573A GB1388977A (en) 1972-09-07 1973-08-13 Thermal switch-heat pipe
DE19732341757 DE2341757A1 (de) 1972-09-07 1973-08-17 Thermisch schaltendes heizrohr
FR7332390A FR2199103B3 (de) 1972-09-07 1973-09-07
JP48101025A JPS4968198A (de) 1972-09-07 1973-09-07

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US00287211A US3854524A (en) 1972-09-07 1972-09-07 Thermal switch-heat pipe

Publications (1)

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US3854524A true US3854524A (en) 1974-12-17

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US00287211A Expired - Lifetime US3854524A (en) 1972-09-07 1972-09-07 Thermal switch-heat pipe

Country Status (5)

Country Link
US (1) US3854524A (de)
JP (1) JPS4968198A (de)
DE (1) DE2341757A1 (de)
FR (1) FR2199103B3 (de)
GB (1) GB1388977A (de)

Cited By (23)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3653011A (en) * 1970-04-15 1972-03-28 Ncr Co Three pole tip read after write transducer
US3935063A (en) * 1973-11-28 1976-01-27 The United States Of America As Represented By The United States Energy Research And Development Administration Emergency heat removal system for a nuclear reactor
FR2313745A1 (fr) * 1975-06-07 1976-12-31 Kernforschungsanlage Juelich Installation pour la production d'energie nucleaire
US4057468A (en) * 1975-03-03 1977-11-08 United Kingdom Atomic Energy Authority Nuclear reactor fuel element sub-assemblies
US4560533A (en) * 1984-08-30 1985-12-24 The United States Of America As Represented By The United States Department Of Energy Fast reactor power plant design having heat pipe heat exchanger
US5360056A (en) * 1993-07-28 1994-11-01 Martin Marietta Energy Systems, Inc. Temperature initiated passive cooling system
US5442668A (en) * 1993-06-03 1995-08-15 Massachusetts Institute Of Technology Passive pressure tube light water cooled and moderated reactor
US20030167721A1 (en) * 2003-05-14 2003-09-11 Hunter Stanley F. Protecting Building Frames from Fire and Heat to Avoid Catastrophic Failure
US20080123797A1 (en) * 2006-11-28 2008-05-29 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Automated nuclear power reactor for long-term operation
US20080123795A1 (en) * 2006-11-28 2008-05-29 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Controllable long term operation of a nuclear reactor
US20080232535A1 (en) * 2006-11-28 2008-09-25 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Modular nuclear fission reactor
US20090175402A1 (en) * 2006-11-28 2009-07-09 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Method and system for providing fuel in a nuclear reactor
US20090225920A1 (en) * 2006-11-28 2009-09-10 Searete Llc, A Limited Liability Corporation Of The State Of Delaware System and method for operating a modular nuclear fission deflagration wave reactor
US20090232268A1 (en) * 2006-11-28 2009-09-17 Searete Llc, A Limited Liability Corporation Of The State Of Delaware System and method for operating a modular nuclear fission deflagration wave reactor
US20090252273A1 (en) * 2006-11-28 2009-10-08 John Rogers Gilleland Automated nuclear power reactor for long-term operation
US20090285348A1 (en) * 2008-05-15 2009-11-19 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat pipe fission fuel element
US20090285349A1 (en) * 2008-05-15 2009-11-19 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat pipe fission fuel element
US20100150292A1 (en) * 2006-11-28 2010-06-17 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Controllable long term operation of a nuclear reactor
CN103377730A (zh) * 2012-04-27 2013-10-30 上海核工程研究设计院 一种以安全壳内水箱为热源的分离式空气冷却热阱
CN103377734A (zh) * 2012-04-27 2013-10-30 上海核工程研究设计院 一种带有分离式空气冷却热阱的下沉式安全壳
US9230695B2 (en) 2006-11-28 2016-01-05 Terrapower, Llc Nuclear fission igniter
US9236150B2 (en) 2009-11-02 2016-01-12 Terrapower, Llc Standing wave nuclear fission reactor and methods
US9269461B2 (en) 2006-11-28 2016-02-23 Terrapower, Llc Method and system for providing fuel in a nuclear reactor

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2506498B1 (fr) * 1981-05-22 1986-03-07 Commissariat Energie Atomique Reacteur nucleaire a neutrons rapides muni de dispositifs d'evacuation de la puissance residuelle
GB8422852D0 (en) * 1984-09-11 1984-11-07 Atomic Energy Authority Uk Heat pipe stabilised specimen container

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US1987119A (en) * 1932-06-20 1935-01-08 Richard H Long Heater for fluids
US2313087A (en) * 1940-09-11 1943-03-09 Warren S Parr Liquid cooling device
US2350348A (en) * 1942-12-21 1944-06-06 Gen Motors Corp Heat transfer device
US3229759A (en) * 1963-12-02 1966-01-18 George M Grover Evaporation-condensation heat transfer device
US3405299A (en) * 1967-01-27 1968-10-08 Rca Corp Vaporizable medium type heat exchanger for electron tubes
US3490718A (en) * 1967-02-01 1970-01-20 Nasa Capillary radiator
DE1937782A1 (de) * 1969-07-25 1971-02-04 Bbc Brown Boveri & Cie Waermerohr
US3613778A (en) * 1969-03-03 1971-10-19 Northrop Corp Flat plate heat pipe with structural wicks
US3613774A (en) * 1969-10-08 1971-10-19 Sanders Associates Inc Unilateral heat transfer apparatus
US3638023A (en) * 1969-11-07 1972-01-25 Atomic Energy Commission Radioisotopic power source

Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1987119A (en) * 1932-06-20 1935-01-08 Richard H Long Heater for fluids
US2313087A (en) * 1940-09-11 1943-03-09 Warren S Parr Liquid cooling device
US2350348A (en) * 1942-12-21 1944-06-06 Gen Motors Corp Heat transfer device
US3229759A (en) * 1963-12-02 1966-01-18 George M Grover Evaporation-condensation heat transfer device
US3405299A (en) * 1967-01-27 1968-10-08 Rca Corp Vaporizable medium type heat exchanger for electron tubes
US3490718A (en) * 1967-02-01 1970-01-20 Nasa Capillary radiator
US3613778A (en) * 1969-03-03 1971-10-19 Northrop Corp Flat plate heat pipe with structural wicks
DE1937782A1 (de) * 1969-07-25 1971-02-04 Bbc Brown Boveri & Cie Waermerohr
US3613774A (en) * 1969-10-08 1971-10-19 Sanders Associates Inc Unilateral heat transfer apparatus
US3638023A (en) * 1969-11-07 1972-01-25 Atomic Energy Commission Radioisotopic power source

Cited By (37)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3653011A (en) * 1970-04-15 1972-03-28 Ncr Co Three pole tip read after write transducer
US3935063A (en) * 1973-11-28 1976-01-27 The United States Of America As Represented By The United States Energy Research And Development Administration Emergency heat removal system for a nuclear reactor
US4057468A (en) * 1975-03-03 1977-11-08 United Kingdom Atomic Energy Authority Nuclear reactor fuel element sub-assemblies
FR2313745A1 (fr) * 1975-06-07 1976-12-31 Kernforschungsanlage Juelich Installation pour la production d'energie nucleaire
US4560533A (en) * 1984-08-30 1985-12-24 The United States Of America As Represented By The United States Department Of Energy Fast reactor power plant design having heat pipe heat exchanger
US5442668A (en) * 1993-06-03 1995-08-15 Massachusetts Institute Of Technology Passive pressure tube light water cooled and moderated reactor
US5360056A (en) * 1993-07-28 1994-11-01 Martin Marietta Energy Systems, Inc. Temperature initiated passive cooling system
US20030167721A1 (en) * 2003-05-14 2003-09-11 Hunter Stanley F. Protecting Building Frames from Fire and Heat to Avoid Catastrophic Failure
US9275759B2 (en) 2006-11-28 2016-03-01 Terrapower, Llc Modular nuclear fission reactor
US9734922B2 (en) 2006-11-28 2017-08-15 Terrapower, Llc System and method for operating a modular nuclear fission deflagration wave reactor
US20080232535A1 (en) * 2006-11-28 2008-09-25 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Modular nuclear fission reactor
US20090175402A1 (en) * 2006-11-28 2009-07-09 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Method and system for providing fuel in a nuclear reactor
US20090225920A1 (en) * 2006-11-28 2009-09-10 Searete Llc, A Limited Liability Corporation Of The State Of Delaware System and method for operating a modular nuclear fission deflagration wave reactor
US20090232268A1 (en) * 2006-11-28 2009-09-17 Searete Llc, A Limited Liability Corporation Of The State Of Delaware System and method for operating a modular nuclear fission deflagration wave reactor
US20090252273A1 (en) * 2006-11-28 2009-10-08 John Rogers Gilleland Automated nuclear power reactor for long-term operation
US10706979B2 (en) 2006-11-28 2020-07-07 TerraPower, LLC. Controlling spatial position of a propagating nuclear fission deflagration wave within a burning wavefront heat generating region
US9899106B2 (en) 2006-11-28 2018-02-20 Terrapower, Llc Method and system for providing fuel in a nuclear reactor
US20100150292A1 (en) * 2006-11-28 2010-06-17 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Controllable long term operation of a nuclear reactor
US9831004B2 (en) 2006-11-28 2017-11-28 Terrapower, Llc Controllable long term operation of a nuclear reactor
US20080123795A1 (en) * 2006-11-28 2008-05-29 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Controllable long term operation of a nuclear reactor
US8971474B2 (en) 2006-11-28 2015-03-03 Terrapower, Llc Automated nuclear power reactor for long-term operation
US20080123797A1 (en) * 2006-11-28 2008-05-29 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Automated nuclear power reactor for long-term operation
US9269461B2 (en) 2006-11-28 2016-02-23 Terrapower, Llc Method and system for providing fuel in a nuclear reactor
US9214246B2 (en) 2006-11-28 2015-12-15 Terrapower, Llc System and method for operating a modular nuclear fission deflagration wave reactor
US9230695B2 (en) 2006-11-28 2016-01-05 Terrapower, Llc Nuclear fission igniter
US10304572B2 (en) 2008-02-12 2019-05-28 Terrapower, Llc Nuclear fission igniter
US9793014B2 (en) * 2008-05-15 2017-10-17 Terrapower, Llc Heat pipe fission fuel element
US20090285349A1 (en) * 2008-05-15 2009-11-19 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat pipe fission fuel element
US20090285348A1 (en) * 2008-05-15 2009-11-19 Searete Llc, A Limited Liability Corporation Of The State Of Delaware Heat pipe fission fuel element
US9236150B2 (en) 2009-11-02 2016-01-12 Terrapower, Llc Standing wave nuclear fission reactor and methods
US9401228B2 (en) 2009-11-02 2016-07-26 Terrapower, Llc Standing wave nuclear fission reactor and methods
US9653187B2 (en) 2009-11-02 2017-05-16 Terrapower, Llc Standing wave nuclear fission reactor and methods
US11482344B2 (en) 2009-11-02 2022-10-25 Terrapower, Llc Standing wave nuclear fission reactor and methods
CN103377730B (zh) * 2012-04-27 2015-08-26 上海核工程研究设计院 一种以安全壳内水箱为热源的分离式空气冷却热阱
CN103377734B (zh) * 2012-04-27 2015-08-26 上海核工程研究设计院 一种带有分离式空气冷却热阱的下沉式安全壳
CN103377734A (zh) * 2012-04-27 2013-10-30 上海核工程研究设计院 一种带有分离式空气冷却热阱的下沉式安全壳
CN103377730A (zh) * 2012-04-27 2013-10-30 上海核工程研究设计院 一种以安全壳内水箱为热源的分离式空气冷却热阱

Also Published As

Publication number Publication date
GB1388977A (en) 1975-04-03
FR2199103A1 (de) 1974-04-05
FR2199103B3 (de) 1976-08-06
DE2341757A1 (de) 1974-03-14
JPS4968198A (de) 1974-07-02

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