BE684620A - - Google Patents
Info
- Publication number
- BE684620A BE684620A BE684620DA BE684620A BE 684620 A BE684620 A BE 684620A BE 684620D A BE684620D A BE 684620DA BE 684620 A BE684620 A BE 684620A
- Authority
- BE
- Belgium
Links
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/06—Sealing-plugs
- G21C13/067—Sealing-plugs for tubes, e.g. standpipes; Locking devices for plugs
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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
- G21C1/14—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
- 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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/34—Spacer grids
- G21C3/348—Spacer grids formed of assembled non-intersecting strips
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/20—Disposition of shock-absorbing devices ; Braking arrangements
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
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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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Particle Accelerators (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB47442/63A GB1086060A (en) | 1963-12-02 | 1963-12-02 | Improvements in or relating to nuclear reactors |
GB32379/65A GB1112346A (en) | 1963-12-02 | 1965-07-28 | Improvements relating to nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
BE684620A true BE684620A (xx) | 1967-01-26 |
Family
ID=26261344
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
BE684620D BE684620A (xx) | 1963-12-02 | 1966-07-26 |
Country Status (4)
Country | Link |
---|---|
US (1) | US3346459A (xx) |
BE (1) | BE684620A (xx) |
FR (2) | FR90327E (xx) |
GB (2) | GB1112346A (xx) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2477753A1 (fr) * | 1980-03-05 | 1981-09-11 | Kraftwerk Union Ag | Element combustible pour reacteur nucleaire avec barres de commande d'efficacite accrue |
FR2517869A1 (fr) * | 1981-12-04 | 1983-06-10 | Framatome Sa | Dispositif d'arret complementaire pour un reacteur nucleaire sous-modere |
EP0240335A2 (en) * | 1986-04-04 | 1987-10-07 | Westinghouse Electric Corporation | Pressurized water reactor having improved calandria assembly |
Families Citing this family (32)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3861999A (en) * | 1967-04-14 | 1975-01-21 | Combustion Eng | Nuclear reactor arrangement and method of operating safe effective to increase the thermal amargin in high power density regions |
US3481832A (en) * | 1967-04-14 | 1969-12-02 | Combustion Eng | Nuclear reactor core and control element arrangement |
US3475273A (en) * | 1967-12-05 | 1969-10-28 | Combustion Eng | Nuclear reactor fuel assembly |
DE1807986A1 (de) * | 1968-11-06 | 1970-06-11 | Euratom | Verfahren und Vorrichtung zur gleichmaessigen Kuehlmittelverteilung auf den Heizflaechen in einem metallgekuehlten Reaktor oder Verdampfer |
BE793195A (fr) * | 1971-12-23 | 1973-04-16 | Combustion Eng | Reacteur nucleaire equipe d'un dispositif hydraulique individuel pour actionner chaque barre de commande |
US3940311A (en) * | 1972-01-21 | 1976-02-24 | Westinghouse Electric Corporation | Nuclear reactor internals construction and failed fuel rod detection system |
US3855059A (en) * | 1972-05-11 | 1974-12-17 | M Groves | Hydraulic system for nuclear reactors with hydraulically driven control rods |
JPS52156900U (xx) * | 1972-06-02 | 1977-11-29 | ||
US3977940A (en) * | 1972-06-02 | 1976-08-31 | Westinghouse Electric Corporation | Emergency cooling system for nuclear reactors |
US3816245A (en) * | 1972-06-27 | 1974-06-11 | Combustion Eng | Emergency core coolant system utilizing an inactive plenum |
US3849257A (en) * | 1972-06-28 | 1974-11-19 | Combustion Eng | Guide structure for control elements |
US4035230A (en) * | 1973-02-20 | 1977-07-12 | Combustion Engineering, Inc. | Shock buffer for nuclear control assembly |
CA1027679A (en) * | 1973-07-31 | 1978-03-07 | Walter E. Desmarchais | Emergency core cooling system for a nuclear reactor |
FR2264368B1 (xx) * | 1974-03-12 | 1977-09-23 | Commissariat Energie Atomique | |
GB1474938A (en) * | 1974-04-29 | 1977-05-25 | Nuclear Power Co Ltd | Nuclear reactors |
SE384593B (sv) * | 1974-08-29 | 1976-05-10 | Asea Atom Ab | Kokvattenreaktor |
GB1464297A (en) * | 1974-09-17 | 1977-02-09 | Atomic Energy Authority Uk | Nuclear reactors |
GB1491232A (en) * | 1974-10-25 | 1977-11-09 | Nuclear Power Co Ltd | Nuclear reactors |
JPS531792A (en) * | 1976-06-28 | 1978-01-10 | Toshiba Corp | Control rod driving device |
US4073684A (en) * | 1976-09-27 | 1978-02-14 | Combustion Engineering, Inc. | Releasable extension shaft coupling |
US4231843A (en) * | 1977-08-02 | 1980-11-04 | Westinghouse Electric Corp. | Guide tube flow diffuser |
FR2416532A1 (fr) * | 1978-02-06 | 1979-08-31 | Commissariat Energie Atomique | Perfectionnements aux reacteurs nucleaires a eau pressurisee |
FR2544539B1 (fr) * | 1983-04-15 | 1985-10-18 | Novatome | Dispositif de freinage de l'element mobile d'un assemblage absorbant d'un reacteur nucleaire a neutrons rapides |
US4657726A (en) * | 1984-06-22 | 1987-04-14 | Westinghouse Electric Corp. | Moderator control apparatus for a nuclear reactor fuel assembly |
US4687621A (en) * | 1984-08-06 | 1987-08-18 | Westinghouse Electric Corp. | Nuclear fuel assembly with improved spectral shift-producing rods |
US4684495A (en) * | 1984-11-16 | 1987-08-04 | Westinghouse Electric Corp. | Fuel assembly bottom nozzle with integral debris trap |
US4683103A (en) * | 1985-02-12 | 1987-07-28 | Westinghouse Electric Corp. | Spectral shift apparatus and method for a nuclear reactor fuel assembly |
JPS6238393A (ja) * | 1985-08-14 | 1987-02-19 | 株式会社日立製作所 | 非常用炉心冷却方法及び装置 |
US4778645A (en) * | 1985-12-09 | 1988-10-18 | Westinghouse Electric Corp. | Pressurized water reactor having disconnectable two-piece drive rod assemblies, and related methods of assembly and maintenance operations |
FR2608306B1 (fr) * | 1986-12-10 | 1989-03-31 | Framatome Sa | Dispositif d'amortissement de chute de barres absorbantes pour assemblage de combustible nucleaire |
KR101389836B1 (ko) * | 2012-08-16 | 2014-04-29 | 한국원자력연구원 | 분리형 안전주입탱크 |
CN110111913B (zh) * | 2018-09-13 | 2022-02-11 | 中国核动力研究设计院 | 六边形套管型燃料堆芯中子注量率测量的试验堆芯及方法 |
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1965
- 1965-07-28 GB GB32379/65A patent/GB1112346A/en not_active Expired
- 1965-09-07 GB GB38241/65A patent/GB1131307A/en not_active Expired
-
1966
- 1966-07-18 US US565764A patent/US3346459A/en not_active Expired - Lifetime
- 1966-07-26 FR FR70886A patent/FR90327E/fr not_active Expired
- 1966-07-26 BE BE684620D patent/BE684620A/xx unknown
- 1966-09-05 FR FR75236A patent/FR91128E/fr not_active Expired
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2477753A1 (fr) * | 1980-03-05 | 1981-09-11 | Kraftwerk Union Ag | Element combustible pour reacteur nucleaire avec barres de commande d'efficacite accrue |
FR2517869A1 (fr) * | 1981-12-04 | 1983-06-10 | Framatome Sa | Dispositif d'arret complementaire pour un reacteur nucleaire sous-modere |
EP0081429A1 (fr) * | 1981-12-04 | 1983-06-15 | Framatome | Dispositif d'arrêt complémentaire pour un réacteur nucléaire sous-modéré refroidi à l'eau |
EP0240335A2 (en) * | 1986-04-04 | 1987-10-07 | Westinghouse Electric Corporation | Pressurized water reactor having improved calandria assembly |
EP0240335A3 (en) * | 1986-04-04 | 1988-09-28 | Westinghouse Electric Corporation | Pressurized water reactor having improved calandria assembly |
Also Published As
Publication number | Publication date |
---|---|
FR90327E (fr) | 1967-11-24 |
US3346459A (en) | 1967-10-10 |
GB1112346A (en) | 1968-05-01 |
GB1131307A (en) | 1968-10-23 |
FR91128E (fr) | 1968-04-19 |