GB1241456A - Nuclear reactor fuel assembly - Google Patents
Nuclear reactor fuel assemblyInfo
- Publication number
- GB1241456A GB1241456A GB59521/68A GB5952168A GB1241456A GB 1241456 A GB1241456 A GB 1241456A GB 59521/68 A GB59521/68 A GB 59521/68A GB 5952168 A GB5952168 A GB 5952168A GB 1241456 A GB1241456 A GB 1241456A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- fissile
- per cent
- fuel elements
- atom per
- 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
- 239000003758 nuclear fuel Substances 0.000 title abstract 3
- 239000000446 fuel Substances 0.000 abstract 15
- 230000004907 flux Effects 0.000 abstract 2
- 238000005457 optimization Methods 0.000 abstract 2
- 238000009835 boiling Methods 0.000 abstract 1
- 230000004992 fission Effects 0.000 abstract 1
- 238000007493 shaping process Methods 0.000 abstract 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 1
Classifications
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
-
- 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
- G21C3/328—Relative disposition of the elements in the bundle lattice
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1,241,456. Fuel elements. GENERAL ELECTRIC CO. 13 Dec., 1968 [15 Dec., 1967], No. 59521/68. Heading G6C. A nuclear fuel element assembly comprises fuel elements arranged in a plurality of groups including an inner group and at least one outer group arranged concentrically around the inner group, the fuel of the elements of a first one of the groups having an initial predetermined enrichment of fissile Pu, and the initial Pu content (if any) of the fuel of the other or at least one other group being markedly different from that of the first. The Pu may be concentrated in the outer fuel elements of the assembly near the regions of highest neutron moderation, i.e. near zones of lowest thermal neutron energy, which arrangement provides for optimization of fuel cycle costs and fuel reliability. Alternatively, the Pu may be concentrated in the inner fuel elements of the assembly, which arrnagement provides for optimization of power and critical heat flux shaping by taking advantage of the increase in the ratio of the thermal fission cross-section of fissile Pu to that of fissile and of the unique higher heat flux capability of the central fuel elements of a boiling water reactor fuel assembly. In the first of these two embodiments, the outer fuel elements contain 1 to 2 atom per cent fissile Pu mixed with depleted or natural U of 0.25 to 0À71 atom per cent fissile U content, while the inner fuel elements contain U fuel of about 3 atom per cent fissile U content. In the second embodiment, the inner fuel elements contain 1 to 2 atom per cent fissile Pu mixed with U of 0À3 to 2 atom per cent fissile U content, while the outer fuel elements contain U fuel of 2 to 3 atom per cent fissile U content.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US69104467A | 1967-12-15 | 1967-12-15 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1241456A true GB1241456A (en) | 1971-08-04 |
Family
ID=24774945
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB59521/68A Expired GB1241456A (en) | 1967-12-15 | 1968-12-13 | Nuclear reactor fuel assembly |
Country Status (10)
| Country | Link |
|---|---|
| BE (1) | BE725473A (en) |
| CH (1) | CH499177A (en) |
| DE (1) | DE1814641B2 (en) |
| ES (1) | ES361211A1 (en) |
| FI (1) | FI49089C (en) |
| FR (1) | FR1598423A (en) |
| GB (1) | GB1241456A (en) |
| IL (1) | IL31145A (en) |
| NL (1) | NL6817982A (en) |
| SE (1) | SE345032B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2221079A (en) * | 1988-07-19 | 1990-01-24 | Atomic Energy Authority Uk | A method and apparatus for inhibiting thermal cycling |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0065697B1 (en) * | 1981-05-15 | 1985-09-11 | Hitachi, Ltd. | Fuel assembly |
| FR2606201B1 (en) * | 1986-11-03 | 1988-12-02 | Electricite De France | METHOD FOR MANAGING THE HEART OF A PRESSURIZED WATER NUCLEAR REACTOR |
| US5089210A (en) * | 1990-03-12 | 1992-02-18 | General Electric Company | Mox fuel assembly design |
-
1968
- 1968-11-22 IL IL31145A patent/IL31145A/en unknown
- 1968-12-07 ES ES361211A patent/ES361211A1/en not_active Expired
- 1968-12-12 SE SE17038/68A patent/SE345032B/xx unknown
- 1968-12-12 CH CH1855168A patent/CH499177A/en not_active IP Right Cessation
- 1968-12-13 GB GB59521/68A patent/GB1241456A/en not_active Expired
- 1968-12-13 FR FR1598423D patent/FR1598423A/fr not_active Expired
- 1968-12-13 DE DE19681814641 patent/DE1814641B2/en active Pending
- 1968-12-13 NL NL6817982A patent/NL6817982A/xx not_active Application Discontinuation
- 1968-12-13 BE BE725473A patent/BE725473A/fr unknown
- 1968-12-13 FI FI683586A patent/FI49089C/en active
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB2221079A (en) * | 1988-07-19 | 1990-01-24 | Atomic Energy Authority Uk | A method and apparatus for inhibiting thermal cycling |
Also Published As
| Publication number | Publication date |
|---|---|
| NL6817982A (en) | 1969-06-17 |
| IL31145A0 (en) | 1969-02-27 |
| IL31145A (en) | 1973-03-30 |
| BE725473A (en) | 1969-06-13 |
| ES361211A1 (en) | 1972-01-01 |
| FR1598423A (en) | 1970-07-06 |
| DE1814641B2 (en) | 1973-04-12 |
| FI49089C (en) | 1975-03-10 |
| SE345032B (en) | 1972-05-08 |
| CH499177A (en) | 1970-11-15 |
| FI49089B (en) | 1974-12-02 |
| DE1814641A1 (en) | 1969-07-24 |
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