Impact of meltdown-accident modeling developments on PWR analysis
Conference
·
OSTI ID:5091387
Models recently incorporated into a new version of the MARCH computer code have altered earlier estimates of some parameter responses during meltdown accidents of PWRs. These models include improved fuel-coolant heat transfer models, new core radiative heat transfer models, improved in-vessel flashing models, improved models for burning of combustible gases in containment, and CORCON1 models for core-concrete interactions. Studies performed with these models have been used to identify and, in some cases, bound meltdown accident analysis uncertainties.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA); Energy, Inc., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5091387
- Report Number(s):
- SAND-82-0283C; CONF-820802-9; ON: DE82020406
- Country of Publication:
- United States
- Language:
- English
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