GB1246760A - Method of exchanging the moderator and fuel of a nuclear reactor, and reactor employing the method - Google Patents
Method of exchanging the moderator and fuel of a nuclear reactor, and reactor employing the methodInfo
- Publication number
- GB1246760A GB1246760A GB43203/70A GB4320370A GB1246760A GB 1246760 A GB1246760 A GB 1246760A GB 43203/70 A GB43203/70 A GB 43203/70A GB 4320370 A GB4320370 A GB 4320370A GB 1246760 A GB1246760 A GB 1246760A
- Authority
- GB
- United Kingdom
- Prior art keywords
- blocks
- core
- reactor
- fuel elements
- channels
- 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
- 239000000446 fuel Substances 0.000 title abstract 7
- 239000002826 coolant Substances 0.000 abstract 2
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 abstract 1
- 229910002804 graphite Inorganic materials 0.000 abstract 1
- 239000010439 graphite Substances 0.000 abstract 1
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
-
- 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
- G21C19/20—Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
-
- 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)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CH1376269A CH504758A (de) | 1969-09-11 | 1969-09-11 | Verfahren zum Austausch von Moderator und Brennstoff eines Kernreaktors, und Reaktor zur Durchführung des Verfahrens |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1246760A true GB1246760A (en) | 1971-09-22 |
Family
ID=4395091
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB43203/70A Expired GB1246760A (en) | 1969-09-11 | 1970-09-09 | Method of exchanging the moderator and fuel of a nuclear reactor, and reactor employing the method |
Country Status (4)
Country | Link |
---|---|
CH (1) | CH504758A (enrdf_load_stackoverflow) |
DE (2) | DE6940264U (enrdf_load_stackoverflow) |
FR (1) | FR2061662B1 (enrdf_load_stackoverflow) |
GB (1) | GB1246760A (enrdf_load_stackoverflow) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4086133A (en) * | 1976-09-07 | 1978-04-25 | General Atomic Company | Nuclear reactor core refueling method |
US4243487A (en) * | 1977-05-03 | 1981-01-06 | Hochtemperatur-Kernkraftwerk Gmbh (Hkg) Gemeinsames Europaisches Unternehmen | Gas-cooled high temperature nuclear reactors |
CN114171222A (zh) * | 2021-11-25 | 2022-03-11 | 中国工程物理研究院核物理与化学研究所 | 一种反应堆换料系统、在线装料、卸料及换料方法 |
Family Cites Families (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE548462A (enrdf_load_stackoverflow) * | 1955-06-10 | |||
GB800388A (en) * | 1956-02-03 | 1958-08-27 | Gen Electric Co Ltd | Improvements in or relating to nuclear reactors |
US3383286A (en) * | 1966-09-27 | 1968-05-14 | Atomic Energy Commission Usa | Core element handling system |
-
1969
- 1969-09-11 CH CH1376269A patent/CH504758A/de not_active IP Right Cessation
- 1969-10-16 DE DE19696940264U patent/DE6940264U/de not_active Expired
- 1969-10-16 DE DE19691952145 patent/DE1952145A1/de active Pending
-
1970
- 1970-09-09 GB GB43203/70A patent/GB1246760A/en not_active Expired
- 1970-09-09 FR FR7032717A patent/FR2061662B1/fr not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4086133A (en) * | 1976-09-07 | 1978-04-25 | General Atomic Company | Nuclear reactor core refueling method |
US4243487A (en) * | 1977-05-03 | 1981-01-06 | Hochtemperatur-Kernkraftwerk Gmbh (Hkg) Gemeinsames Europaisches Unternehmen | Gas-cooled high temperature nuclear reactors |
CN114171222A (zh) * | 2021-11-25 | 2022-03-11 | 中国工程物理研究院核物理与化学研究所 | 一种反应堆换料系统、在线装料、卸料及换料方法 |
CN114171222B (zh) * | 2021-11-25 | 2024-06-04 | 中国工程物理研究院核物理与化学研究所 | 一种反应堆换料系统、在线装料、卸料及换料方法 |
Also Published As
Publication number | Publication date |
---|---|
DE6940264U (de) | 1971-09-16 |
FR2061662A1 (enrdf_load_stackoverflow) | 1971-06-25 |
CH504758A (de) | 1971-03-15 |
DE1952145A1 (de) | 1971-03-18 |
FR2061662B1 (enrdf_load_stackoverflow) | 1975-01-10 |
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