GB882651A - Improvements in or relating to nuclear reactors - Google Patents
Improvements in or relating to nuclear reactorsInfo
- Publication number
- GB882651A GB882651A GB36617/57A GB3661757A GB882651A GB 882651 A GB882651 A GB 882651A GB 36617/57 A GB36617/57 A GB 36617/57A GB 3661757 A GB3661757 A GB 3661757A GB 882651 A GB882651 A GB 882651A
- Authority
- GB
- United Kingdom
- Prior art keywords
- elements
- beryllia
- nov
- fuel
- minimum
- 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
- G21C1/04—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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
- G21C3/18—Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
-
- 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
- G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
882,651. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. Nov. 13, 1958 [Nov. 25, 1957(2)], Nos. 36617/57 and 36618/57. Class 39(4) In a heterogeneous nuclear reactor core element the fuel plates 2 are mounted in the faces of the hexagonal beryllia rod 1. The element is contained in a stainless steel, or chromised mild steel sheath 3. The elements are stacked together with separation 5 formed by the ceramic spacers 4 and the pressurised cooling fluid, such as air or oxygen, flows in 5, between the members. The fuel plates may be formed by pressing or sintering enriched uranium dioxide in beryllia or alumina. The rods 1 are built up of separate segments. As the steel sheathing passes through zones of minimum reactor flux the neutron loss is a minimum. Breeder elements may be formed by substituting thorium dioxide for uranium dioxide.
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB36617/57A GB882651A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to nuclear reactors |
FR1208777D FR1208777A (en) | 1957-11-25 | 1958-11-20 | Atomic batteries |
DEU5765A DE1097582B (en) | 1957-11-25 | 1958-11-24 | Nuclear reactor fuel element |
CH6660058A CH365151A (en) | 1957-11-25 | 1958-11-25 | Nuclear reactor with fuel masses arranged like a grid |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB36617/57A GB882651A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB882651A true GB882651A (en) | 1961-11-15 |
Family
ID=10389742
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB36617/57A Expired GB882651A (en) | 1957-11-25 | 1957-11-25 | Improvements in or relating to nuclear reactors |
Country Status (4)
Country | Link |
---|---|
CH (1) | CH365151A (en) |
DE (1) | DE1097582B (en) |
FR (1) | FR1208777A (en) |
GB (1) | GB882651A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110111913A (en) * | 2018-09-13 | 2019-08-09 | 中国核动力研究设计院 | The test reactor core and method of hexagon thimble tube fuel reactor core neutron fluence rate measurement |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL275721A (en) * | 1961-03-09 | |||
CN114121308A (en) * | 2021-11-24 | 2022-03-01 | 西安交通大学 | Reactor core structure of lead bismuth cooling fast neutron research reactor with ultra-high flux |
Family Cites Families (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB768078A (en) * | 1954-03-31 | 1957-02-13 | Ca Atomic Energy Ltd | Improvements relating to fuel rod assemblies for nuclear reactors |
BE550790A (en) * | 1955-04-30 |
-
1957
- 1957-11-25 GB GB36617/57A patent/GB882651A/en not_active Expired
-
1958
- 1958-11-20 FR FR1208777D patent/FR1208777A/en not_active Expired
- 1958-11-24 DE DEU5765A patent/DE1097582B/en active Pending
- 1958-11-25 CH CH6660058A patent/CH365151A/en unknown
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110111913A (en) * | 2018-09-13 | 2019-08-09 | 中国核动力研究设计院 | The test reactor core and method of hexagon thimble tube fuel reactor core neutron fluence rate measurement |
CN110111913B (en) * | 2018-09-13 | 2022-02-11 | 中国核动力研究设计院 | Test reactor core and method for measuring neutron fluence rate of hexagonal sleeve type fuel reactor core |
Also Published As
Publication number | Publication date |
---|---|
FR1208777A (en) | 1960-02-25 |
DE1097582B (en) | 1961-01-19 |
CH365151A (en) | 1962-10-31 |
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