Published December 1996
| Version v1
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NSSR experiment with 50 MWd/kgU PWR fuel under an RIA condition
- 1. Japan Atomic Energy Research Inst., Tokai (Japan). Dept. of Reactor Safety Research
Description
Results obtained in the NSRR power burst experiments with irradiated PWR fuel rods with fuel burnup up to 50 MWd/kgU are described and discussed in this paper. Data concerning test method, test fuel rod, pulse irradiation, transient records during the pulse and post irradiation examination are described, and interpretations and discussions on fission gas release and fuel pellet fragmentation are presented. During the pulse-irradiation experiment with 50 MWd/kgU PWR fuel rod, the fuel rod failed at considerably low energy deposition level, and large amount of fission gas release and fragmentation of fuel pellets were observed. (author). 6 refs, 11 figs, 5 tabs
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Additional details
Publishing Information
- Imprint Title
- Behaviour of LWR core materials under accident conditions. Proceedings of a technical committee meeting
- Imprint Pagination
- 299 p.
- Journal Page Range
- p. 265-279.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--921
Conference
- Title
- Technical committee meeting on behaviour of LWR core materials under accident conditions.
- Dates
- 9-13 Oct 1995.
- Place
- Dimitrovgrad (Russian Federation).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28023764
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BURNUP; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FRAGMENTATION; FUEL PELLETS; POST-IRRADIATION EXAMINATION; PULSE GENERATORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY EXPERIMENTS; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; DATA; ELECTRONIC EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FUNCTION GENERATORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS