Survey of MELCOR assessment
MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants and is being developed at Sandia National Laboratories for the USNRC and the USDOE. The entire spectrum of severe accident phenomena, including reactor coolant system and containment thermal/hydraulic response, core heatup, degradation and relocation, and fission product release and transport, is treated in MELCOR in a unified framework for both BWRs and PWRS. MELCOR was the first of the severe accident analysis codes to undergo a formal review process, and one of the major conclusions of the MELCOR Peer Review was the need for a more comprehensive and more systematic program of MELCOR assessment. Since then, a number of assessment analyses have been completed and more assessment calculations axe under way. This paper presents a review of MELCOR verification, validation and assessment to date.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10191146
- Report Number(s):
- SAND--92-1723C; CONF-930352--4; ON: DE93002297
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
99 GENERAL AND MISCELLANEOUS
990200
BWR TYPE REACTORS
CONTAINMENT
CORIUM
EVALUATION
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
M CODES
MATHEMATICS AND COMPUTERS
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY