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FR1455672A - Cooling system for nuclear reactors - Google Patents

Cooling system for nuclear reactors

Info

Publication number
FR1455672A
FR1455672A FR40351A FR40351A FR1455672A FR 1455672 A FR1455672 A FR 1455672A FR 40351 A FR40351 A FR 40351A FR 40351 A FR40351 A FR 40351A FR 1455672 A FR1455672 A FR 1455672A
Authority
FR
France
Prior art keywords
heat
heat pipes
fuel
vapour
pipes
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
Application number
FR40351A
Other languages
French (fr)
Inventor
Josef Bohdansky
Claus-Adolf Busse
George Maurice Grover
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
European Atomic Energy Community Euratom
Original Assignee
European Atomic Energy Community Euratom
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by European Atomic Energy Community Euratom filed Critical European Atomic Energy Community Euratom
Application granted granted Critical
Publication of FR1455672A publication Critical patent/FR1455672A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D7/00Arrangements for direct production of electric energy from fusion or fission reactions
    • G21D7/04Arrangements for direct production of electric energy from fusion or fission reactions using thermoelectric elements or thermoionic converters
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/24Promoting flow of the coolant
    • G21C15/257Promoting flow of the coolant using heat-pipes
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

1,108,499. Reactors. EUROPEAN ATOM ENERGY COMMUNITY (EURATOM). 13 Dec., 1965 [14 Dec., 1964], No. 52862/65. Heading G6C. A nuclear reactor has one or more heat pipes as a means for extracting the heat of reaction. A heat pipe is a heat transfer device comprising a container, condensable vapour, and capillary means disposed within the container for the transport of the condensed vapour from a cooler region of the container to a hotter region. The vapour is driven from the hotter region to the cooler region by the difference in vapour pressure. The temperature drop along the heat pipe is powers of ten lower than in the case of conventional heat transports and a nearly uniform temperature distribution is therefore established along the entire pipe surface. In a specific example, portions of heat pipes are disposed in, and thermally coupled to, passageways in the fuel elements, moderator and reflector of a reactor core to form evaporator regions, the non-coupled portions extending outwardly from the reactor core to form condenser regions. The inner walls of the heat pipes are covered with wicks, e.g. of niobium, of suitable capillary structure, the pores sizes of the wicks being sufficiently small to produce capillary action. Tubular fuel elements may be separately mounted on the heat pipes or the fuel may be coated directly on the outer surfaces of the heat pipes. A suitable fuel is a Mo-UO 2 , cermet. The fuel heat pipes are preferably of Ta and contain Ag as the heat carrier fluid, operating at a temperature of about 1800‹ C., while the moderator and reflector heat pipes are preferably of Nb and contain Cs as the heat carrier fluid. The moderator is ZrH 2 and is separated from the fuel elements by electrical insulation and thermal shields. The condenser regions of the fuel heat pipes each terminate in an emitter electrode of a thermionic converter. The front faces of the heat pipes can each directly constitute an emitter electrode or be vapour-plated with an electron emissive layer. The collector electrodes of the thermionic converter are each coupled to a heat pipe for the removal of heat generated. The collector heat pipes are preferably formed of Nb- Zr alloy and contain Li as the heat carrier fluid.
FR40351A 1964-12-14 1965-11-30 Cooling system for nuclear reactors Expired FR1455672A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEE0028354 1964-12-14

Publications (1)

Publication Number Publication Date
FR1455672A true FR1455672A (en) 1966-10-14

Family

ID=7073293

Family Applications (1)

Application Number Title Priority Date Filing Date
FR40351A Expired FR1455672A (en) 1964-12-14 1965-11-30 Cooling system for nuclear reactors

Country Status (6)

Country Link
BE (1) BE673462A (en)
DE (1) DE1464912C3 (en)
FR (1) FR1455672A (en)
GB (1) GB1108499A (en)
LU (1) LU50048A1 (en)
NL (1) NL6515397A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2313745A1 (en) * 1975-06-07 1976-12-31 Kernforschungsanlage Juelich INSTALLATION FOR THE PRODUCTION OF NUCLEAR ENERGY

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4808240A (en) * 1987-09-08 1989-02-28 The United States Of America As Represented By The United States Department Of Energy Stacked vapor fed amtec modules
RU2680250C1 (en) * 2018-04-13 2019-02-19 Акционерное общество "Государственный научный центр Российской Федерации - Физико-энергетический институт имени А.И. Лейпунского" Active zone of the nuclear reactor
CN110310751A (en) * 2019-06-29 2019-10-08 西安交通大学 A kind of nuclear reactor power supply of the two-way insertion reactor core of heat pipe
CN110634580B (en) * 2019-09-26 2022-05-13 哈尔滨工程大学 Heat pipe type deep sea application nuclear reactor system
US20240170168A1 (en) * 2022-11-19 2024-05-23 Westinghouse Electric Company Llc Solid-state fluid thermal bonded heat pipe micro-reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2313745A1 (en) * 1975-06-07 1976-12-31 Kernforschungsanlage Juelich INSTALLATION FOR THE PRODUCTION OF NUCLEAR ENERGY

Also Published As

Publication number Publication date
DE1464912A1 (en) 1969-04-17
DE1464912C3 (en) 1975-02-20
LU50048A1 (en) 1967-06-13
NL6515397A (en) 1966-06-15
GB1108499A (en) 1968-04-03
DE1464912B2 (en) 1974-07-04
BE673462A (en) 1966-06-08

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