VICTORIA-92 pretest analyses of PHEBUS-FPT0
FPT0 is the first of six tests that are scheduled to be conducted in an experimental reactor in Cadarache, France. The test apparatus consists of an in-pile fuel bundle, an upper plenum, a hot leg, a steam generator, a cold leg, and a small containment. Thus, the test is integral in the sense that it attempts to simulate all of the processes that would be operative in a severe nuclear accident. In FPT0, the fuel will be trace irradiated; in subsequent tests high burn-up fuel will be used. This report discusses separate pretest analyses of the FPT0 fuel bundle and primary circuit have been conducted using the USNRC`s source term code, VICTORIA-92. Predictions for release of fission product, control rod, and structural elements from the test section are compared with those given by CORSOR-M. In general, the releases predicted by VICTORIA-92 occur earlier than those predicted by CORSOR-M. The other notable difference is that U release is predicted to be on a par with that of the control rod elements; CORSOR-M predicts U release to be about 2 orders of magnitude greater.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States); Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 10133239
- Report Number(s):
- SAND--93-2275; ON: DE94008314; BR: GB0103012
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220600
220900
99 GENERAL AND MISCELLANEOUS
990200
AEROSOLS
C CODES
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
EXPERIMENT PLANNING
FISSION PRODUCT RELEASE
FUEL ELEMENTS
HEAT TRANSFER
HYDRAULICS
MATHEMATICS AND COMPUTERS
RADIATION TRANSPORT
RADIOACTIVITY TRANSPORT
REACTOR ACCIDENTS
REACTOR SAFETY
RESEARCH REACTORS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SOURCE TERMS
V CODES