The development of grain face porosity in irradiated oxide fuel
Description
The predominant mode of fission gas release occurs through atomic diffusion to the grain boundaries. In oxide fuels the fission gases initially precipitate as an array of small lenticular bubbles. The arrival of additional gas and vacancies causes these bubbles to grow and coalesce into fewer, larger bubbles. Depending on the irradiation conditions and temperature, these bubbles may develop either as circular lenticular pores or as extended multi-lobed pores. Eventually the pores may intersect the grain edges where pathways may be formed, which enable the gases to migrate to the outer geometry of the fuel and hence to the gap and the pin-free volume. Recent extensive PIE campaigns on irradiated fuels have provided a large database of intergranular porosity development and, from these, models of bubble growth, coalescence, morphological relaxation and venting have been developed. (author)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-19715-X
- Imprint Title
- Fission gas behaviour in water reactor fuels
- Imprint Pagination
- 559 p.
- Journal Page Range
- p. 189-198
Conference
- Title
- Seminar on fission gas behaviour in water reactor fuels
- Dates
- 26-29 Sep 2000
- Place
- Cadarache (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 33012514
- Subject category
- S36: MATERIALS SCIENCE; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BUBBLE GROWTH; COALESCENCE; FISSION PRODUCT RELEASE; GRAIN BOUNDARIES; POROSITY; SPENT FUELS; SWELLING; VACANCIES
- Descriptors DEC
- CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DEFORMATION; ENERGY SOURCES; FUELS; MATERIALS; MICROSTRUCTURE; NUCLEAR FUELS; POINT DEFECTS; REACTOR MATERIALS
Optional Information
- Notes
- 8 refs.