Integrated ex-vessel source term analysis with the CONTAIN 1. 1 computer code
Conference
·
OSTI ID:6965461
Important new phenomenological models and code improvements, which will be available in Version 1.1 of the CONTAIN code, are discussed, and results of a thirteen cell demonstration calculation presented. CONTAIN has been developed for the USNRC as a best-estimate code for modeling nuclear reactor containment behavior under severe accident conditions. CONTAIN 1.1 has major new capabilities for treating core-concrete interactions and boiling water reactor (BWR) containment systems. The CORCON and VANESA codes have been merged with CONTAIN for modeling the behavior of molten core interactions with concrete, and suppression pool models have been developed for use in BWR containment calculations. Significant improvements made to existing models of radiation heat transfer, pool boiling, fission product transport, and aerosol flow are also discussed. Calculational results for a BWR station blackout accident sequence illustrate the wide range of coupled physical phenomena that CONTAIN can model.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6965461
- Report Number(s):
- SAND-86-2119C; CONF-8610135-44; ON: DE87004240
- Country of Publication:
- United States
- Language:
- English
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