Nuclear fuel element
Description
Since a great temperature gradient is caused in the radial direction of a fuel pellet, the upper and the lower ends of the pellet are extended outwardly and deformed into a saddle-like form, by which the end face of the pellet is brought into contact with a fuel can, to apply high stress and distortion to the fuel can. If nuclear fission products should exert on the stress-strained portion, the possibility of causing stress corrosion cracks is increased. Then, in the present invention, an aluminium thin film is formed as a second layer at the inside of a lined cladding tube comprising a pure zirconium layer disposed to the inner surface of a fuel can made of a zirconium-based alloy. This can protect the zirconium of the first coating layer and prevent selective corrosion due to corrosive fission products. Further, since aluminum is excellent in ductility and easily deformed, stress concentration can be moderated. (T.M.)
Availability note (English)
Available from JAPIO. Also available from INPADOC.Additional details
Publishing Information
- Imprint Pagination
- 4 p.
- IPC:
- Int. Cl. G21C3/20.
- IPC
- Int. Cl. G21C3/20.
- Patent number
- JP patent document 3-37596/A/
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 22077458
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ALUMINIUM; DEFORMATION; FUEL CANS; FUEL ELEMENTS; FUEL PELLETS; STRESS CORROSION; SURFACE COATING; TEMPERATURE GRADIENTS; THIN FILMS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; CORROSION; DEPOSITION; ELEMENTS; FILMS; METALS; REACTOR COMPONENTS; REACTORS; TRANSITION ELEMENTS; ZIRCONIUM ALLOYS
Optional Information
- Secondary number(s)
- JP patent application 1-171136.