GB1216468A - Improvements relating to nuclear reactor fuel elements - Google Patents
Improvements relating to nuclear reactor fuel elementsInfo
- Publication number
- GB1216468A GB1216468A GB56382/66A GB5638266A GB1216468A GB 1216468 A GB1216468 A GB 1216468A GB 56382/66 A GB56382/66 A GB 56382/66A GB 5638266 A GB5638266 A GB 5638266A GB 1216468 A GB1216468 A GB 1216468A
- Authority
- GB
- United Kingdom
- Prior art keywords
- region
- voidage
- sheath
- fuel
- carbide
- 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 1
- 239000000446 fuel Substances 0.000 abstract 5
- 239000000463 material Substances 0.000 abstract 3
- 238000000034 method Methods 0.000 abstract 3
- 239000008188 pellet Substances 0.000 abstract 3
- 239000000919 ceramic Substances 0.000 abstract 2
- 150000001875 compounds Chemical class 0.000 abstract 2
- 238000004519 manufacturing process Methods 0.000 abstract 2
- 239000011248 coating agent Substances 0.000 abstract 1
- 238000000576 coating method Methods 0.000 abstract 1
- 230000008961 swelling Effects 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
- G21C3/02—Fuel elements
- G21C3/28—Fuel elements with fissile or breeder material in solid form within a non-active casing
-
- 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
-
- 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
- G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
-
- 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)
- Carbon And Carbon Compounds (AREA)
Abstract
1,216,468. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 6 Feb., 1968 [16 Dec., 1966], No. 56382/66. Addition to 948,479. Heading G6C. A fuel element, for operation in a fast nuclear reactor, employs ceramic fuel comprising a depleted or low enrichment region surrounded by a high enrichment region, with a sheath enclosing both regions, the high enrichment region having up to 40% voidage, including distributed voidage. Suitable fuel material is Pu/U oxide or carbide, or U-233/Th oxide or carbide. One fabrication procedure is to stack cylindrical or annular pellets of depleted or low enrichment material within a sheath and load highly enriched material in the annulus between the stack and the sheath by a vibrocompaction procedure. As the highly enriched outer region will be required to undergo a high fractional burn-up, its relative density should be kept low, possibly 60 to 70% of the theoretical density. The inner region can have a higher theoretical density but local voidage must be provided to accommodate fuel swelling there also. A central hole in the pellets is desirable and may provide part of the total voidage of the inner region. In addition to the internal voidage -distributed throughout the outer region of high enrichment a gap may be left between the outer region and the sheath. This gap would be gas-filled, e.g. initially with He. An alternative method of manufacture is to apply a ceramic Pu or U-233 compound as a coating on pellets forming the inner region. For compatibility reasons, the inner and outer regions are desirably the same type of chemical compound, i.e. oxide or carbide.
Priority Applications (5)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE624223D BE624223A (en) | 1966-12-16 | ||
GB39407/61A GB948479A (en) | 1961-11-03 | 1961-11-03 | Improvements in or relating to fuel elements for nuclear reactors |
US233135A US3240679A (en) | 1961-11-03 | 1962-10-25 | Fuel elements for nuclear reactors |
FR913807A FR1339744A (en) | 1962-10-29 | 1962-10-29 | Improvements to fuel cartridges for nuclear reactors |
GB56382/66A GB1216468A (en) | 1966-12-16 | 1966-12-16 | Improvements relating to nuclear reactor fuel elements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB56382/66A GB1216468A (en) | 1966-12-16 | 1966-12-16 | Improvements relating to nuclear reactor fuel elements |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1216468A true GB1216468A (en) | 1970-12-23 |
Family
ID=10476472
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB56382/66A Expired GB1216468A (en) | 1961-11-03 | 1966-12-16 | Improvements relating to nuclear reactor fuel elements |
Country Status (2)
Country | Link |
---|---|
BE (1) | BE624223A (en) |
GB (1) | GB1216468A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0098696A1 (en) * | 1982-06-24 | 1984-01-18 | Exxon Nuclear Company Inc. | Fuel element for nuclear reactor |
-
0
- BE BE624223D patent/BE624223A/xx unknown
-
1966
- 1966-12-16 GB GB56382/66A patent/GB1216468A/en not_active Expired
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0098696A1 (en) * | 1982-06-24 | 1984-01-18 | Exxon Nuclear Company Inc. | Fuel element for nuclear reactor |
Also Published As
Publication number | Publication date |
---|---|
BE624223A (en) |
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