Published 1988 | Version v1
Book

Sefdan analyses of NRU full-length high-temperature tests

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

Part of:
Proceedings of the international ENS/ANS conference on thermal reactor safety. Volume 1

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).

Optional Information

Notes
Imprint:Actes de la Conference Internationale ENS/ANS sur la surete des reacteurs thermiques. Volume 1.