Data for FUMEX: Results from fuel behavior studies at the OECD Halden Reactor Project for model validation and development
Creators
- 1. Institutt for Energiteknikk, Halden (Norway). OECD Halden Reaktor Projekt
Description
Investigations of phenomena associated with extended or high burn-up are an important part of the fuel and materials testing programme carried out at the OECD Halden Reactor Project. The in-core studies comprise long term fuel rod behavior as well as the response to power ramps. Performance is assessed through measurements of fuel centre temperature, rod pressure, elongation of cladding and fuel stack, and cladding diameter changes obtained during full power reactor operation. Data from fuel behavior studies at the OECD Halden Reactor Project, provided for the IAEA co-ordinated research programme FUMEX, are used to elucidate short and long-term developments of fuel behavior. The examples comprise: fuel conductivity degradation manifested as a gradual temperature increase with burn-up; the influence of a combination of small gap/high fission gas release on fuel centre temperature (situation at high burn-up); fission gas release during normal operation and power ramps, and the possibility of a burn-up enhancement; PCMI reflected by cladding elongation, also for the case of a nominally open gap, and the change of interaction onset with burn-up. (author). 10 refs, 9 figs, 1 tab
Files
28068597.pdf
Files
(439.1 kB)
| Name | Size | Download all |
|---|---|---|
|
md5:aeac45040fea4248684ee00c930117ed
|
439.1 kB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Water reactor fuel element modelling at high burnup and its experimental support. Proceedings of a technical committee meeting
- Imprint Pagination
- 559 p.
- Journal Page Range
- p. 39-54.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--957
Conference
- Title
- Technical committee meeting on water reactor fuel element modelling at high burnup and its experimental support.
- Dates
- 19-23 Sep 1994.
- Place
- Windermere (United Kingdom).
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 28068597
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BURNUP; EXPERIMENTAL DATA; FISSION PRODUCT RELEASE; FUEL ELEMENTS; HBWR REACTOR; SIMULATION; SIZE; TEMPERATURE DEPENDENCE; THEORETICAL DATA; THERMAL CONDUCTIVITY; VARIATIONS
- Descriptors DEC
- BHWR TYPE REACTORS; DATA; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; NUMERICAL DATA; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES