ES283111A1 - Un método para eliminar calor y los productos de fisión y reactor nuclear de contacto directo que lo realiza - Google Patents
Un método para eliminar calor y los productos de fisión y reactor nuclear de contacto directo que lo realizaInfo
- Publication number
- ES283111A1 ES283111A1 ES283111A ES283111A ES283111A1 ES 283111 A1 ES283111 A1 ES 283111A1 ES 283111 A ES283111 A ES 283111A ES 283111 A ES283111 A ES 283111A ES 283111 A1 ES283111 A1 ES 283111A1
- Authority
- ES
- Spain
- Prior art keywords
- translation
- machine
- legally binding
- google translate
- fision
- 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
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/02—Control of nuclear reaction by using self-regulating properties of reactor materials, e.g. Doppler effect
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/24—Homogeneous reactors, i.e. in which the fuel and moderator present an effectively homogeneous medium to the neutrons
-
- 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
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
- G21C19/50—Reprocessing of irradiated fuel of irradiated fluid fuel, e.g. regeneration of fuels while the reactor is in operation
-
- 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
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/904—Moderator, reflector, or coolant materials
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/904—Moderator, reflector, or coolant materials
- Y10S376/906—Metal
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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Physical Or Chemical Processes And Apparatus (AREA)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US159195A US3161570A (en) | 1961-12-13 | 1961-12-13 | Homogeneous-liquid metal-fast reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
ES283111A1 true ES283111A1 (es) | 1963-10-16 |
Family
ID=22571498
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
ES283111A Expired ES283111A1 (es) | 1961-12-13 | 1962-12-05 | Un método para eliminar calor y los productos de fisión y reactor nuclear de contacto directo que lo realiza |
Country Status (8)
Families Citing this family (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3262856A (en) * | 1965-01-14 | 1966-07-26 | Edward S Bettis | Fused-salt-fueled, molten-metal-cooled power breeder reactor system |
US3377251A (en) * | 1967-05-24 | 1968-04-09 | Atomic Energy Commission Usa | Nuclear reactor for use in space |
FR2101019B1 (US07981874-20110719-C00313.png) * | 1970-08-07 | 1973-12-21 | Commissariat Energie Atomique | |
FR2291580A1 (fr) * | 1974-11-14 | 1976-06-11 | Commissariat Energie Atomique | Dispositif de protection thermique de la cuve d'un reacteur |
US4331512A (en) * | 1979-04-23 | 1982-05-25 | Electric Power Research Institute, Inc. | Nuclear reactor guard vessel arrangement |
US9734922B2 (en) | 2006-11-28 | 2017-08-15 | Terrapower, Llc | System and method for operating a modular nuclear fission deflagration wave reactor |
US9831004B2 (en) | 2006-11-28 | 2017-11-28 | Terrapower, Llc | Controllable long term operation of a nuclear reactor |
US9230695B2 (en) | 2006-11-28 | 2016-01-05 | Terrapower, Llc | Nuclear fission igniter |
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 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2865827A (en) * | 1955-05-27 | 1958-12-23 | Orrington E Dwyer | Power generation from liquid metal nuclear fuel |
US2910417A (en) * | 1955-05-27 | 1959-10-27 | Robert J Teitel | Uranium bismuthide dispersion in molten metal |
US2837476A (en) * | 1956-01-27 | 1958-06-03 | Harold M Busey | Steam stirred homogeneous nuclear reactor |
US3050454A (en) * | 1957-03-13 | 1962-08-21 | Exxon Research Engineering Co | High flux homogeneous reactor with circulating fissile material |
US3041263A (en) * | 1957-12-05 | 1962-06-26 | Robert M Kiehn | Molten plutonium fueled fast breeder reactor |
US3029142A (en) * | 1960-05-24 | 1962-04-10 | Arthur S Coffinberry | Reactor fuel scavenging means |
-
0
- NL NL286671D patent/NL286671A/xx unknown
- BE BE625221D patent/BE625221A/xx unknown
-
1961
- 1961-12-13 US US159195A patent/US3161570A/en not_active Expired - Lifetime
-
1962
- 1962-10-29 GB GB40858/62A patent/GB963528A/en not_active Expired
- 1962-11-19 SE SE12368/62A patent/SE307200B/xx unknown
- 1962-12-04 CH CH1428662A patent/CH395355A/fr unknown
- 1962-12-05 DE DEP1271A patent/DE1271270B/de active Pending
- 1962-12-05 ES ES283111A patent/ES283111A1/es not_active Expired
Also Published As
Publication number | Publication date |
---|---|
SE307200B (US07981874-20110719-C00313.png) | 1968-12-23 |
GB963528A (en) | 1964-07-08 |
BE625221A (US07981874-20110719-C00313.png) | 1900-01-01 |
CH395355A (fr) | 1965-07-15 |
US3161570A (en) | 1964-12-15 |
DE1271270B (de) | 1968-06-27 |
NL286671A (US07981874-20110719-C00313.png) | 1900-01-01 |
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