BE707209A - - Google Patents
Info
- Publication number
- BE707209A BE707209A BE707209A BE707209A BE707209A BE 707209 A BE707209 A BE 707209A BE 707209 A BE707209 A BE 707209A BE 707209 A BE707209 A BE 707209A BE 707209 A BE707209 A BE 707209A
- Authority
- BE
- Belgium
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
- G21C1/04—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
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/04—Arrangements for expansion and contraction
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- 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
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
-
- 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)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB53223/66A GB1137279A (en) | 1966-11-28 | 1966-11-28 | Nuclear reactors |
GB2517867 | 1967-05-31 |
Publications (1)
Publication Number | Publication Date |
---|---|
BE707209A true BE707209A (fr) | 1968-05-28 |
Family
ID=26257549
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
BE707209A BE707209A (fr) | 1966-11-28 | 1967-11-28 |
Country Status (4)
Country | Link |
---|---|
US (1) | US3544425A (fr) |
BE (1) | BE707209A (fr) |
DE (1) | DE1614949A1 (fr) |
GB (1) | GB1137279A (fr) |
Families Citing this family (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3936350A (en) * | 1970-11-25 | 1976-02-03 | Westinghouse Electric Corporation | Nuclear reactor having thermally compensated support structure for a fuel assembly |
GB1306037A (fr) * | 1971-01-21 | 1973-02-07 | ||
GB1382423A (en) * | 1971-02-25 | 1975-01-29 | British Nuclear Design Constr | Nuclear reactor boiler systems |
DE2706216A1 (de) * | 1977-02-14 | 1978-08-17 | Kraftwerk Union Ag | Berstgesicherte kernreaktoranlage mit druckwasserreaktor |
DE2719613C2 (de) * | 1977-05-03 | 1985-04-04 | Hochtemperatur-Kernkraftwerk GmbH (HKG) Gemeinsames Europäisches Unternehmen, 4701 Uentrop | Gasgekühlter Hochtemperatur-Kernreaktor |
DE2854155A1 (de) * | 1978-12-15 | 1980-07-03 | Hochtemperatur Reaktorbau Gmbh | Gasgekuehlter hochtemperaturreaktor mit einer mit gasdurchlaessen versehenen tragkonstruktion |
FR2484125A1 (fr) * | 1980-06-06 | 1981-12-11 | Framatome Sa | Dispositif de cloisonnement du coeur d'un reacteur nucleaire |
FR2501893B1 (fr) * | 1981-03-13 | 1985-11-15 | Framatome Sa | Reacteur nucleaire a cloisonnement de coeur par tiges et plaques entretoises |
US4596689A (en) * | 1982-08-27 | 1986-06-24 | Ga Technologies Inc. | Lateral restraint assembly for reactor core |
DE3344527A1 (de) * | 1983-12-09 | 1985-06-20 | Hochtemperatur-Reaktorbau GmbH, 4600 Dortmund | Kernreaktoranlage |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2863815A (en) * | 1953-07-23 | 1958-12-09 | Moore Richard Valentine | Nuclear reactor |
US3127046A (en) * | 1959-07-16 | 1964-03-31 | Pressure vessels |
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1966
- 1966-11-28 GB GB53223/66A patent/GB1137279A/en not_active Expired
-
1967
- 1967-11-25 DE DE1967U0014439 patent/DE1614949A1/de active Pending
- 1967-11-27 US US685874A patent/US3544425A/en not_active Expired - Lifetime
- 1967-11-28 BE BE707209A patent/BE707209A/fr unknown
Also Published As
Publication number | Publication date |
---|---|
GB1137279A (en) | 1968-12-18 |
DE1614949A1 (de) | 1971-01-14 |
US3544425A (en) | 1970-12-01 |