FR1455672A - Cooling system for nuclear reactors - Google Patents
Cooling system for nuclear reactorsInfo
- 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
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D7/00—Arrangements for direct production of electric energy from fusion or fission reactions
- G21D7/04—Arrangements for direct production of electric energy from fusion or fission reactions using thermoelectric elements or thermoionic converters
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
-
- 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
-
- 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
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.
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)
| 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)
| 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 |
-
1964
- 1964-12-14 DE DE1464912A patent/DE1464912C3/en not_active Expired
-
1965
- 1965-11-26 NL NL6515397A patent/NL6515397A/xx unknown
- 1965-11-30 FR FR40351A patent/FR1455672A/en not_active Expired
- 1965-12-08 BE BE673462D patent/BE673462A/xx unknown
- 1965-12-13 GB GB52862/65A patent/GB1108499A/en not_active Expired
- 1965-12-13 LU LU50048D patent/LU50048A1/xx unknown
Cited By (1)
| 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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