Numerical analysis of the PHEBUS containment thermal hydraulics
- Nuclear Power Engineering Corp., Tokyo (Japan)
- Toshiba Advanced System Corp., Kawasaki (Japan)
An international project, the PHEBUS Fission Project Program (von der Hardt et al., 1994), is being carried out at Cadarache, France. Six integral in-pile tests, FPT0--FPT5, have been planned in the project to evaluate the behavior of fission products (FPs) released from a light water reactor during a severe accident. This paper describes numerical analysis of the PHEBUS FP steady-state benchmark problems and the first in-pile transient test, FPT0. A two-dimensional code has been newly developed to predict thermal hydraulics in the containment vessel, including air, steam and hydrogen transport and steam condensation. A degradation factor correlation, which plays an important role in the predictions for the condensation heat transfer in the presence of noncondensable gases, has been developed and incorporated into the code. The calculation results show that the code can accurately and rapidly predict complicated phenomena in the PHEBUS containment vessel.
- OSTI ID:
- 271890
- Report Number(s):
- CONF-960306--; ISBN 0-7918-1226-X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
CONTAINMENT SYSTEMS
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
REACTOR ACCIDENTS
REACTOR COOLING SYSTEMS
REACTOR CORES
REACTOR SAFETY EXPERIMENTS
T CODES
TEST FACILITIES
THEORETICAL DATA
VAPOR CONDENSATION
WATER COOLED REACTORS