VICTORIA-92 and its application to the PHEBUS-FPT0 test
- Sandia National Labs., Albuquerque, NM (United States)
- Science Applications International Corp., Albuquerque, NM (United States)
VICTORIA-92 is a mechanistic computer code designed to analyze fission product behavior within the reactor coolant system (RCS) during a severe accident. It provides detailed prediction of the release from the fuel and transport in the RCS of radionuclides and non-radioactive materials during core degradation. These predictions account for the chemical and aerosol processes that affect radionuclide behavior. Coupling of detailed chemistry and aerosol packages is a unique feature of VICTORIA: it allows exploration of issues involving deposition, revaporization, and reentrainment that cannot be resolved with other codes.This document describes a new version, VICTORIA-92, which was recently released.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6832065
- Report Number(s):
- SAND-92-179/C; CONF-921007--7; ON: DE93003996
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220502 -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AEROSOLS
CHEMICAL REACTIONS
COLLOIDS
COMPUTER CODES
COOLING SYSTEMS
DEPOSITION
DISPERSIONS
EVAPORATION
FISSION PRODUCT RELEASE
FUEL CANS
FUEL ELEMENTS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PHASE TRANSFORMATIONS
POWER PLANTS
RADIATION TRANSPORT
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SOLS
THERMAL POWER PLANTS
V CODES