Fission product behaviour and fuel rod chemistry at extended burnup: Results, models and programmes of analytical experiments carried out at the CEA, Grenoble
- 1. CEA Centre d'Etudes de Grenoble, 38 (France)
Description
Of the analytical experiments carried out at CEA to study fuel behaviour at high burnups, special mention should be made of the study of the effects of moderate transients on fission gas release (importance of cracking associated with power variations), and SEM examination of fracture surface of various fuels (analysis of bubble populations and precipitates of associated metallic fission products). Several factors must be considered when analysing the results: radial specific power profile and its thermal effect, fission gas creation, oxygen balance, density and open porosity, gaseous swelling. This paper describes the principle of various tools (calculations or experiments) used to obtain information on all these points. Finally, a brief discussion is given of the study programmes relating to the effect of O/M ratio on fuel behaviour and to the major problem of caesium retention. (author). 11 refs, 4 figs
Additional details
Publishing Information
- Imprint Title
- Fission gas release and fuel rod chemistry related to extended burnup
- Imprint Pagination
- 235 p.
- Journal Page Range
- p. 98-103.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--697
Conference
- Title
- Technical committee meeting on fission gas release and fuel rod chemistry related to extended burnup.
- Dates
- 28 Apr - 1 May 1992.
- Place
- Pembroke, ON (Canada).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 24050752
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CRACKING; FISSION PRODUCT RELEASE; FUEL RODS; GASES; PWR TYPE REACTORS; TRANSIENTS
- Descriptors DEC
- CHEMICAL REACTIONS; DECOMPOSITION; ENRICHED URANIUM REACTORS; FLUIDS; FUEL ELEMENTS; POWER REACTORS; PYROLYSIS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS