MELCOR-calculated in-containment source terms with and without the BH package
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:552530
- Oak Ridge National Lab., TN (United States)
This study compares in-containment source terms calculated with the MELCOR version 1.8.3 (1.8 PZ) severe accident code with and without the lower plenum debris bed model, also called the BH package. The source terms were calculated for a low-pressure, short-term station blackout severe accident at the Grand Gulf Nuclear Station, for which a best-estimate MELCOR deck is available.
- OSTI ID:
- 552530
- Report Number(s):
- CONF-971125--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 77; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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