FR1483407A - Nuclear reactor - Google Patents
Nuclear reactorInfo
- Publication number
- FR1483407A FR1483407A FR65566A FR65566A FR1483407A FR 1483407 A FR1483407 A FR 1483407A FR 65566 A FR65566 A FR 65566A FR 65566 A FR65566 A FR 65566A FR 1483407 A FR1483407 A FR 1483407A
- Authority
- FR
- France
- Prior art keywords
- nuclear reactor
- nuclear
- reactor
- 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
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/022—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core
- G21C1/024—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders characterised by the design or properties of the core where the core is divided in zones with fuel and zones with breeding material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
- G21C11/022—Biological shielding ; Neutron or gamma shielding inside the reactor vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/02—Biological shielding ; Neutron or gamma shielding
- G21C11/028—Biological shielding ; Neutron or gamma shielding characterised by the form or by the material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C11/00—Shielding structurally associated with the reactor
- G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/08—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from moderating material
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
-
- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- 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
- G21C15/22—Structural association of coolant tubes with headers
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/08—Means for preventing undesired asymmetric expansion of the complete structure ; Stretching devices, pins
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
- G21C5/10—Means for supporting the complete structure
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Health & Medical Sciences (AREA)
- Life Sciences & Earth Sciences (AREA)
- Biomedical Technology (AREA)
- General Health & Medical Sciences (AREA)
- Molecular Biology (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR65566A FR1483407A (en) | 1965-07-08 | 1966-06-15 | Nuclear reactor |
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB29057/65A GB1129363A (en) | 1965-07-08 | 1965-07-08 | Nuclear reactors |
FR65566A FR1483407A (en) | 1965-07-08 | 1966-06-15 | Nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
FR1483407A true FR1483407A (en) | 1967-06-02 |
Family
ID=26171334
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
FR65566A Expired FR1483407A (en) | 1965-07-08 | 1966-06-15 | Nuclear reactor |
Country Status (1)
Country | Link |
---|---|
FR (1) | FR1483407A (en) |
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2067167A1 (en) * | 1968-11-08 | 1971-08-20 | Nuclear Power Group Ltd | |
FR2099666A1 (en) * | 1970-07-29 | 1972-03-17 | British Nuclear Design Constr | |
FR2108896A1 (en) * | 1970-10-16 | 1972-05-26 | Commissariat Energie Atomique | |
FR2211716A1 (en) * | 1972-12-27 | 1974-07-19 | Commissariat Energie Atomique | Composite heat transport medium - using a solid e.g. graphite dispersed in a gas e.g. helium for high temperature heat transmission e.g. from nuclear reactors |
FR2382264A1 (en) * | 1977-03-03 | 1978-09-29 | Ght Hochtemperaturreak Tech | MIXER AND DISPERSER DEVICE FOR HIGH TEMPERATURE GAS |
FR2389201A1 (en) * | 1977-04-26 | 1978-11-24 | Hochtemperatur Reaktorbau Gmbh | SUPPORT OF THE CORE OF A GAS-COOLED HIGH-TEMPERATURE REACTOR |
FR2462000A1 (en) * | 1979-07-23 | 1981-02-06 | Hochtemperatur Reaktorbau Gmbh | CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS |
FR2497388A1 (en) * | 1980-12-30 | 1982-07-02 | Commissariat Energie Atomique | NUCLEAR REACTOR COOLED BY A LIQUID METAL AND COMPRISING A COOLED COLD BOTTOM |
-
1966
- 1966-06-15 FR FR65566A patent/FR1483407A/en not_active Expired
Cited By (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2067167A1 (en) * | 1968-11-08 | 1971-08-20 | Nuclear Power Group Ltd | |
FR2099666A1 (en) * | 1970-07-29 | 1972-03-17 | British Nuclear Design Constr | |
FR2108896A1 (en) * | 1970-10-16 | 1972-05-26 | Commissariat Energie Atomique | |
FR2211716A1 (en) * | 1972-12-27 | 1974-07-19 | Commissariat Energie Atomique | Composite heat transport medium - using a solid e.g. graphite dispersed in a gas e.g. helium for high temperature heat transmission e.g. from nuclear reactors |
FR2382264A1 (en) * | 1977-03-03 | 1978-09-29 | Ght Hochtemperaturreak Tech | MIXER AND DISPERSER DEVICE FOR HIGH TEMPERATURE GAS |
FR2389201A1 (en) * | 1977-04-26 | 1978-11-24 | Hochtemperatur Reaktorbau Gmbh | SUPPORT OF THE CORE OF A GAS-COOLED HIGH-TEMPERATURE REACTOR |
FR2462000A1 (en) * | 1979-07-23 | 1981-02-06 | Hochtemperatur Reaktorbau Gmbh | CARRIER BASE FORMED OF A LARGE NUMBER OF GRAPHITE BLOCKS FOR THE HEART OF A NUCLEAR REACTOR WITH SPHERICAL FUEL ELEMENTS |
FR2497388A1 (en) * | 1980-12-30 | 1982-07-02 | Commissariat Energie Atomique | NUCLEAR REACTOR COOLED BY A LIQUID METAL AND COMPRISING A COOLED COLD BOTTOM |
EP0055963A2 (en) * | 1980-12-30 | 1982-07-14 | Commissariat à l'Energie Atomique | Liquid metal cooled nuclear reactor comprising a main vessel cooled at the bottom |
EP0055963A3 (en) * | 1980-12-30 | 1982-08-11 | Commissariat A L'energie Atomique Etablissement De Caractere Scientifique Technique Et Industriel | Liquid metal cooled nuclear reactor comprising a main vessel cooled at the bottom |
US4671922A (en) * | 1980-12-30 | 1987-06-09 | Commissariat A L'energie Atomique | Nuclear reactor cooled by a liquid metal |
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