GB913920A - Improvements in or relating to fuel elements for nuclear reactors - Google Patents
Improvements in or relating to fuel elements for nuclear reactorsInfo
- Publication number
- GB913920A GB913920A GB36292/60A GB3629260A GB913920A GB 913920 A GB913920 A GB 913920A GB 36292/60 A GB36292/60 A GB 36292/60A GB 3629260 A GB3629260 A GB 3629260A GB 913920 A GB913920 A GB 913920A
- Authority
- GB
- United Kingdom
- Prior art keywords
- sheath
- region
- fuel member
- hollow
- breach
- 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
- 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
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
- G21C17/048—Detecting burst slugs characterised by a special construction of fuel elements, e.g. by a confined "tracer"
-
- 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
- G21C3/17—Means for storage or immobilisation of gases in fuel elements
-
- 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
913,920. Nuclear fuel elements. UNITED KINGDOM ATOMIC ENERGY AUTHORITY. Sept. 12, 1961 [Oct. 21, 1960], No. 36292/60. Drawings to Specification. Class 39 (4). A fuel member enclosed in a protective sheath has a region of preferential initial oxidation on its surface and an element is positioned within the sheath in such a way that an increase in volume on oxidation at this region due to ingress of coolant through a leakage in the sheath causes the element to breach the sheath. The element may be in the form of a plug, of stainless steel for example, a disc of fissile material being disposed above the tip so that a strong signal is received on the fission products detection apparatus immediately the tip protrudes through the sheath. Alternatively, the surface of the element may be roughened to allow fission products to escape freely round it. The sheath may be weakened where it covers the element to make penetration easier. The region of preferential initial oxidation may be produced by a hollow on the outer surface of the fuel member, which hollow may contain an insert of a material more readily oxidizable than the fuel member, e.g. a uranium/platinum alloy containing 1% by weight of platinum. With a tubular fuel member, an element having a bore may extend from a region on the hotter, inner surface across the hollow interior and through the opposite wall, any ingressed fluid present passing through the bore to oxidizing the above region which expands and causes the element to breach the sheath.
Priority Applications (4)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
BE609356D BE609356A (en) | 1960-10-21 | ||
GB36292/60A GB913920A (en) | 1960-10-21 | 1960-10-21 | Improvements in or relating to fuel elements for nuclear reactors |
DEU8362A DE1223471B (en) | 1960-10-21 | 1961-09-30 | Device for detecting leaks in the shell of nuclear reactor fuel assemblies |
FR876048A FR1303828A (en) | 1960-10-21 | 1961-10-16 | Fuel cartridge for nuclear reactors |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB36292/60A GB913920A (en) | 1960-10-21 | 1960-10-21 | Improvements in or relating to fuel elements for nuclear reactors |
Publications (1)
Publication Number | Publication Date |
---|---|
GB913920A true GB913920A (en) | 1962-12-28 |
Family
ID=10386784
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB36292/60A Expired GB913920A (en) | 1960-10-21 | 1960-10-21 | Improvements in or relating to fuel elements for nuclear reactors |
Country Status (3)
Country | Link |
---|---|
BE (1) | BE609356A (en) |
DE (1) | DE1223471B (en) |
GB (1) | GB913920A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4036685A (en) * | 1971-07-28 | 1977-07-19 | Siemens Aktiengesellschaft | Method and apparatus for detecting the leak of coolant into the jacket of a nuclear reactor fuel rod |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2855355A (en) * | 1945-11-28 | 1958-10-07 | Leo A Ohlinger | Jacketed uranium slug |
-
0
- BE BE609356D patent/BE609356A/xx unknown
-
1960
- 1960-10-21 GB GB36292/60A patent/GB913920A/en not_active Expired
-
1961
- 1961-09-30 DE DEU8362A patent/DE1223471B/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4036685A (en) * | 1971-07-28 | 1977-07-19 | Siemens Aktiengesellschaft | Method and apparatus for detecting the leak of coolant into the jacket of a nuclear reactor fuel rod |
Also Published As
Publication number | Publication date |
---|---|
BE609356A (en) | |
DE1223471B (en) | 1966-08-25 |
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