GB1248483A - Nuclear reactor core - Google Patents
Nuclear reactor coreInfo
- Publication number
- GB1248483A GB1248483A GB22345/69A GB2234569A GB1248483A GB 1248483 A GB1248483 A GB 1248483A GB 22345/69 A GB22345/69 A GB 22345/69A GB 2234569 A GB2234569 A GB 2234569A GB 1248483 A GB1248483 A GB 1248483A
- Authority
- GB
- United Kingdom
- Prior art keywords
- fuel
- neutron flux
- peripheral
- core
- fissile
- 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 abstract 10
- 230000004907 flux Effects 0.000 abstract 6
- 230000002093 peripheral effect Effects 0.000 abstract 6
- 230000000712 assembly Effects 0.000 abstract 4
- 238000000429 assembly Methods 0.000 abstract 4
- 238000009826 distribution Methods 0.000 abstract 4
- 230000004992 fission Effects 0.000 abstract 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 abstract 4
- 238000009835 boiling Methods 0.000 abstract 1
- 239000002826 coolant Substances 0.000 abstract 1
- 238000010248 power generation Methods 0.000 abstract 1
Classifications
-
- 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
Abstract
1,248,483. Reactors. GENERAL ELECTRIC CO. 1 May, 1969 [2 May, 1968], No. 22345/69. Heading G6C. A reactor core comprises two fissile fuels, one having a greater thermal neutron fission crosssection than the other and being located initially only in a peripheral region of the core. In a boiling water reactor using light water as coolant /moderator and in which the core is surrounded by water acting as a reflector, the peripheral region of the core has a steep gradient of neutron flux of relatively low energy. The fuel assemblies for use in this region comprise a plurality of elongated spaced fuel elements, the initial enrichment of the fissile fuel in these elements being graduated among the elements in inverse relationship to the neutron flux gradient. Fissile Pu may advantageously be mixed with depleted or natural U, each of the fuel elements initially containing at least 0À5 wt. per cent of fissile Pu. The spatial distribution of Pu in each peripheral fuel assembly depends on the geometry of the assembly with respect to the surrounding water reflector, i.e. the number of sides and corners of the assembly adjacent the reflector. In the embodiment described, the peripheral fuel assemblies have two sides and the included edge, or only one side and no edge, or only an edge and no side facing the reflec or, which differences result in different neutron flux distributions across these assemblies. Different spatial distributions of the Pu fuel in these assemblies are therefore required for optimum results. Local power flattening is achieved by placing the fuel of highest enrichment in the positions of minimum thermal neutron flux and vice versa. The mean fission cross-section of Pu in a thermal neutron flux is about 2À7 x that of U. Since the power generation rate is directly proportional to the fission cross-section times the neutron flux, the greater fission cross-section of Pu is an aid in increasing the relative power in the peripheral zone to thereby improve the radial power distribution of the core. The resulting more rapid burn-up of the Pu fuel also aids in matching the refuelling cycle periods of the peripheral and central zones.
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US72607968A | 1968-05-02 | 1968-05-02 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| GB1248483A true GB1248483A (en) | 1971-10-06 |
Family
ID=24917142
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB22345/69A Expired GB1248483A (en) | 1968-05-02 | 1969-05-01 | Nuclear reactor core |
Country Status (7)
| Country | Link |
|---|---|
| BE (1) | BE732368A (en) |
| DE (1) | DE1922593C2 (en) |
| FR (1) | FR2009848A1 (en) |
| GB (1) | GB1248483A (en) |
| IL (1) | IL32076A (en) |
| NL (1) | NL170195C (en) |
| SE (1) | SE373972B (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114496314A (en) * | 2022-02-17 | 2022-05-13 | 中国核动力研究设计院 | Fast neutron thermal neutron concentric circle type partitioned ultrahigh flux reactor core |
| CN115221647A (en) * | 2022-06-08 | 2022-10-21 | 上海交通大学 | Method for realizing volume minimization design of solid reactor core of gas cooled reactor by comprehensive physical thermal analysis |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3039614A1 (en) * | 1980-10-21 | 1982-05-19 | Brown, Boveri & Cie Ag, 6800 Mannheim | Slide movement hand operated switch - has protected keyway staggered profile movement slot to prevent ingress of dirt |
| JPH07119818B2 (en) * | 1990-03-14 | 1995-12-20 | 株式会社日立製作所 | Fuel assembly and reactor |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB1066264A (en) * | 1963-11-15 | 1967-04-26 | Atomic Energy Commission | Nuclear reactor |
| FR1494657A (en) * | 1966-01-06 | 1967-09-08 | Atomic Energy Commission | High power fast neutron breeder reactor |
-
1969
- 1969-04-25 IL IL32076A patent/IL32076A/en unknown
- 1969-04-29 SE SE6906104*A patent/SE373972B/xx unknown
- 1969-04-30 BE BE732368D patent/BE732368A/xx unknown
- 1969-04-30 FR FR6913822A patent/FR2009848A1/en not_active Withdrawn
- 1969-05-01 GB GB22345/69A patent/GB1248483A/en not_active Expired
- 1969-05-02 NL NLAANVRAGE6906717,A patent/NL170195C/en not_active IP Right Cessation
- 1969-05-02 DE DE1922593A patent/DE1922593C2/en not_active Expired
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114496314A (en) * | 2022-02-17 | 2022-05-13 | 中国核动力研究设计院 | Fast neutron thermal neutron concentric circle type partitioned ultrahigh flux reactor core |
| CN114496314B (en) * | 2022-02-17 | 2024-02-13 | 中国核动力研究设计院 | Ultra-high flux reactor core with fast neutron thermal neutron concentric circle type partition |
| CN115221647A (en) * | 2022-06-08 | 2022-10-21 | 上海交通大学 | Method for realizing volume minimization design of solid reactor core of gas cooled reactor by comprehensive physical thermal analysis |
Also Published As
| Publication number | Publication date |
|---|---|
| FR2009848A1 (en) | 1970-02-13 |
| DE1922593C2 (en) | 1981-12-17 |
| NL170195C (en) | 1982-10-01 |
| BE732368A (en) | 1969-10-30 |
| SE373972B (en) | 1975-02-17 |
| IL32076A0 (en) | 1969-07-30 |
| IL32076A (en) | 1972-12-29 |
| NL6906717A (en) | 1969-11-04 |
| NL170195B (en) | 1982-05-03 |
| DE1922593A1 (en) | 1970-07-30 |
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