GB880662A - Improvements relating to nuclear fuel and control rod structure - Google Patents
Improvements relating to nuclear fuel and control rod structureInfo
- Publication number
- GB880662A GB880662A GB31229/59A GB3122959A GB880662A GB 880662 A GB880662 A GB 880662A GB 31229/59 A GB31229/59 A GB 31229/59A GB 3122959 A GB3122959 A GB 3122959A GB 880662 A GB880662 A GB 880662A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- billet
- plate
- rolled
- flat
- 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
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
- G21C21/10—Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching by rolling, e.g. "picture frame" technique
-
- 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
-
- 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
- G21C7/10—Construction of control elements
- G21C7/113—Control elements made of flat elements; Control elements having cruciform cross-section
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Pressure Welding/Diffusion-Bonding (AREA)
Abstract
880,662. Nuclear fuel elements; nuclear reactor control rods. GENERAL ELECTRIC CO. Sept 14, 1959 [Sept. 29, 1958; Oct. 20, 1958], No. 31229/59. Class 39(4) [Also in Group XXII] A nuclear reactor core element (i.e. a fuel or control rod) comprises an elongated plate provided with a plurality of elongated sealed channels of lenticular or irregular but substantially rectangular cross-section containing active nuclear material (i.e. fuel or neutron absorbent material) in the form of closely packed particles the major axis of the cross-section being parallel to the principal exterior surface of the plate. In one arrangement three holes are drilled in a stainless steel billet and filled with powdered uranium dioxide, 20% enriched, which is compacted; the open ends of the holes are sealed and the billet rolled to produce the fuel plate shown in Fig. 2. In another arrangement a stainless steel strip is rolled to form a pair of U-shaped channels with a corrugated strip between them as shown in Fig. 3; the ends of the strip may be welded at 26, 28 or the flanges may be compressed to bond them together. One end of the billet is closed by stamping or forging and the billet is then filled with uranium dioxide powder and its open end closed. The billet is then rolled to produce the flat fuel plate shown in Fig. 4. Flat or curved fuel plates may be secured at their edges to side plates to form a fuel element assembly, Figs. 5 and 6 (not shown). Control rods may be made in the same way using a neutron absorbent such as boron carbide instead of fuel in the billet. A long flat control plate as in Fig. 2 or Fig. 4 may be welded to two short ones to form a cruciform control element, Figs. 7 and 8 (not shown).
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US880662XA | 1958-09-29 | 1958-09-29 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB880662A true GB880662A (en) | 1961-10-25 |
Family
ID=22209190
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB31229/59A Expired GB880662A (en) | 1958-09-29 | 1959-09-14 | Improvements relating to nuclear fuel and control rod structure |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR1235255A (en) |
GB (1) | GB880662A (en) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3156625A (en) * | 1962-10-22 | 1964-11-10 | Harty Harold | Core for a supercritical pressure power reactor |
CN108735317A (en) * | 2018-06-04 | 2018-11-02 | 江苏核电有限公司 | A kind of PWR irradiated fuel assemblies storage lattice cell and manufacturing method |
CN113345611A (en) * | 2021-05-11 | 2021-09-03 | 哈尔滨工程大学 | Multi-rectangular-flow-channel uniform heat release simulation test device for plate-type fuel element |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01221698A (en) * | 1988-03-01 | 1989-09-05 | Toshiba Corp | Control rod |
-
1959
- 1959-09-14 GB GB31229/59A patent/GB880662A/en not_active Expired
- 1959-09-18 FR FR805415A patent/FR1235255A/en not_active Expired
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3156625A (en) * | 1962-10-22 | 1964-11-10 | Harty Harold | Core for a supercritical pressure power reactor |
CN108735317A (en) * | 2018-06-04 | 2018-11-02 | 江苏核电有限公司 | A kind of PWR irradiated fuel assemblies storage lattice cell and manufacturing method |
CN108735317B (en) * | 2018-06-04 | 2024-02-09 | 江苏核电有限公司 | PWR spent fuel assembly storage cell and manufacturing method |
CN113345611A (en) * | 2021-05-11 | 2021-09-03 | 哈尔滨工程大学 | Multi-rectangular-flow-channel uniform heat release simulation test device for plate-type fuel element |
Also Published As
Publication number | Publication date |
---|---|
FR1235255A (en) | 1960-07-01 |
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