Sefdan analyses of NRU full-length high-temperature tests
Creators
Description
Since the reactor accident occurred at the Three Mile Island Unit-2 Reactor (TMI-2) on March 28, 1979, considerable effort has been devoted worldwidely to experimental and analytical researches in order to shed light on the severe fuel damage process. Despite the extensive effort, the process has not been fully understood even in early stage of accident in which the major relocation of fuel rod material does not start. Especially the phenomena not clearly understood were; the maximum temperature of fuel rod to be reached, and the controlling mechanisms on temperature turnaround and on relocation. In order to more profoundly understand such severe fuel damage phenomena, a computer code SEFDAN with one-dimensional core thermal hydraulics was developed in Japan Atomic Energy Research Institute (JAERI), and SEFDAN was applied to analyses of typical severe fuel damage (SFD) tests and accident
Additional details
Additional titles
- Original title (no language)
- Actes de la Conference Internationale ENS/ANS sur la surete des reacteurs thermiques. Volume 1.
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 1
- Imprint Pagination
- 417 p.
- Journal Page Range
- p. 139-150.
Conference
- Title
- International ENS/ANS Conference on thermal reactor safety.
- Dates
- 2-7 Oct 1988.
- Place
- Avignon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21015089
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EVALUATION; FLUID-STRUCTURE INTERACTIONS; HYDRAULICS; MELTDOWN; PWR TYPE REACTORS; S CODES; TEST FACILITIES; THERMODYNAMICS; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ELEMENTS; ENRICHED URANIUM REACTORS; METALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Actes de la Conference Internationale ENS/ANS sur la surete des reacteurs thermiques. Volume 1.