BE627360A - - Google Patents
Info
- Publication number
- BE627360A BE627360A BE627360DA BE627360A BE 627360 A BE627360 A BE 627360A BE 627360D A BE627360D A BE 627360DA BE 627360 A BE627360 A BE 627360A
- Authority
- BE
- Belgium
Links
Classifications
-
- 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
- G21C1/09—Pressure regulating arrangements, i.e. pressurisers
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- 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
-
- 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
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
- G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
- G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
- G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/087—Metallic vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/093—Concrete vessels
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- 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
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
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- 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
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
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- 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)
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB24720/60A GB981424A (en) | 1960-07-15 | 1960-07-15 | Improvements in or relating to heterogeneous nuclear reactors |
GB2334/62A GB1003826A (en) | 1960-07-15 | 1962-01-22 | Improvements in or relating to nuclear reactors |
GB2578662 | 1962-07-05 |
Publications (1)
Publication Number | Publication Date |
---|---|
BE627360A true BE627360A (de) | 1900-01-01 |
Family
ID=27254060
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
BE627360D BE627360A (de) | 1960-07-15 |
Country Status (5)
Country | Link |
---|---|
US (2) | US3212985A (de) |
BE (1) | BE627360A (de) |
DE (1) | DE1202404B (de) |
GB (1) | GB1003826A (de) |
NL (1) | NL288037A (de) |
Families Citing this family (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE627361A (de) * | 1962-07-05 | 1900-01-01 | ||
GB964760A (en) * | 1963-01-08 | 1964-07-22 | Atomic Energy Authority Uk | Nuclear reactor |
US3280004A (en) * | 1963-02-04 | 1966-10-18 | Atomic Energy Authority Uk | Water cooled nuclear reactor with improved core and reflector recirculation system |
FR1414851A (fr) * | 1964-08-27 | 1965-10-22 | Commissariat Energie Atomique | Réacteur nucléaire |
US3346461A (en) * | 1966-03-07 | 1967-10-10 | Gennaro V Notari | Nuclear reactor fuel element |
US3401081A (en) * | 1966-04-28 | 1968-09-10 | Allis Chalmers Mfg Co | Hydraulic holddown for nuclear reactor fuel assembly |
SE424237B (sv) * | 1980-10-29 | 1982-07-05 | Asea Atom Ab | Brensleelement for en kokarreaktor |
US4706613A (en) * | 1986-10-17 | 1987-11-17 | Westinghouse Electric Corp. | Steam generator having an auxiliary recirculation path |
US5120493A (en) * | 1990-07-10 | 1992-06-09 | General Electric Company | Forced-circulation reactor with enhanced natural circulation |
Family Cites Families (16)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2890158A (en) * | 1944-12-19 | 1959-06-09 | Leo A Ohlinger | Neutronic reactor |
US2708656A (en) * | 1944-12-19 | 1955-05-17 | Fermi Enrico | Neutronic reactor |
US2832733A (en) * | 1946-04-23 | 1958-04-29 | Szilard Leo | Heavy water moderated neutronic reactor |
GB796992A (en) * | 1953-04-13 | 1958-06-25 | Atomic Energy Authority Uk | Improvements in or relating to nuclear reactors |
US2958637A (en) * | 1955-09-09 | 1960-11-01 | Standard Oil Co | Conversion of hydrocarbons |
US3016738A (en) * | 1955-09-27 | 1962-01-16 | Eule Martin | Means for supervising the heat development and heat transfer in boilers, furnaces and heat consumers |
BE553050A (de) * | 1955-11-30 | |||
DE1027338B (de) * | 1956-10-06 | 1958-04-03 | Siemens Ag | Kernreaktor mit zwei Druckzonen |
BE563693A (de) * | 1956-10-31 | |||
DE1064652B (de) * | 1957-01-22 | 1959-09-03 | Heinz Maier Leibnitz Dr | Kernreaktor mit zusaetzlicher Erhitzung des Kuehlmittels |
DE1053109B (de) * | 1957-01-26 | 1959-03-19 | Siemens Ag | Heterogener Kernreaktor |
BE565765A (de) * | 1957-03-19 | |||
GB852957A (en) * | 1957-06-24 | 1960-11-02 | Atomic Energy Authority Uk | Improvements in or relating to cooling systems for nuclear reactors |
FR1207124A (fr) * | 1958-08-14 | 1960-02-15 | Commissariat Energie Atomique | Cylindre de barrage pour le contrôle de l'évacuation de l'eau et de la suppression de la hauteur motrice de circulation naturelle dans un réacteur atomique à eau bouilante |
BE583878A (de) * | 1959-06-06 | |||
US3105036A (en) * | 1961-09-05 | 1963-09-24 | Karl H Puechl | Pressurized water reactor core with plutonium burnup |
-
0
- NL NL288037D patent/NL288037A/xx unknown
- BE BE627360D patent/BE627360A/xx unknown
-
1961
- 1961-07-10 DE DEU8168A patent/DE1202404B/de active Pending
-
1962
- 1962-01-22 GB GB2334/62A patent/GB1003826A/en not_active Expired
- 1962-11-19 US US238438A patent/US3212985A/en not_active Expired - Lifetime
- 1962-11-19 US US238446A patent/US3175954A/en not_active Expired - Lifetime
Also Published As
Publication number | Publication date |
---|---|
US3212985A (en) | 1965-10-19 |
NL288037A (de) | 1900-01-01 |
DE1202404B (de) | 1965-10-07 |
GB1003826A (en) | 1965-09-08 |
US3175954A (en) | 1965-03-30 |