Fracture of zircaloy cladding under simulated power ramp conditions
Description
The behaviour of Zircaloy cladding under stresses imposed by fuel dimensional changes is discussed, and results are presented which suggest that correct choice of cladding properties, in particular cold-work level and texture, is important if the probability of low-ductility failures in fuel pins is to be reduced. Evidence is presented, based on laboratory tests and post-irradiation examination of cladding, which leads to the conclusion that failure of Zircaloy can occur by stress-corrosion cracking in the presence of fission product iodine, and it is further demonstrated that the process is strongly stress-dependent. Consideration is also given to the influence of irradiation exposure, strain rate, and adverse stress systems, for instance at pellet ridges or cracks, on the cracking susceptibility of cladding. (author)
Additional details
Publishing Information
- Publisher
- Metals Society.
- Imprint Place
- London
- ISBN
- 0900497971
- Imprint Title
- Physical metallurgy of reactor fuel elements
- Imprint Pagination
- p. 33-36.
Conference
- Title
- International conference on the physical metallurgy of reactor fuel elements.
- Dates
- 2 Sep 1973.
- Place
- Berkeley, UK.
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 8281051
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACKS; FISSION PRODUCTS; FUEL CANS; FUEL-CLADDING INTERACTIONS; IODINE; NUCLEAR FUELS; PERFORMANCE TESTING; PHYSICAL RADIATION EFFECTS; STRESS CORROSION; STRESSES; TEXTURE; ZIRCALOY 2
- Descriptors DEC
- ALLOYS; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; CORROSION; ELEMENTS; ENERGY SOURCES; FUELS; HALOGENS; IRON ADDITIONS; ISOTOPES; NONMETALS; RADIATION EFFECTS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; TESTING; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS