Analysis of fission product revaporization in a BWR Reactor Coolant System during a station blackout accident
This paper presents an analysis of fission product revaporization from the Reactor Coolant System (RCS) following the Reactor Pressure Vessel (RPV) failure. The station blackout accident in a BWR Mark I Power Plant was considered. The TRAPMELT3 models for vaporization, chemisorption, and the decay heating of RCS structures and gases were used and extended beyond the RPV failure in the analysis. The RCS flow models based on the density-difference or pressure-difference between the RCS and containment pedestal region were developed to estimate the RCS outflow which carries the revaporized fission product to the containment. A computer code called REVAP was developed for the analysis. The REVAP code was incorporated with the MARCH, TRAPMELT3 and NAUA codes from the Source Term Code Package (STCP) to estimate the impact of revaporization on environmental release. The results show that the thermal-hydraulic conditions between the RCS and the pedestal region are important factors in determining the magnitude of revaporization and subsequent release of the volatile fission product into the environment. 6 refs., 8 figs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6751597
- Report Number(s):
- BNL-NUREG-41553-Rev.; CONF-881011-19-Rev.; ON: DE89001095
- Resource Relation:
- Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct 1988; Other Information: Paper copy only, copy does not permit microfiche production
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uncertainties in source term estimates for a station blackout accident in a BWR with Mark I containment
MELCOR simulation of long-term station blackout at Peach Bottom
Related Subjects
BWR TYPE REACTORS
REACTOR COOLING SYSTEMS
REACTOR ACCIDENTS
FISSION PRODUCT RELEASE
BLACKOUTS
CONTAINMENT
FISSION PRODUCTS
HEAT TRANSFER
HYDRAULICS
N CODES
R CODES
RADIOACTIVE EFFLUENTS
REACTOR SAFETY
SOURCE TERMS
T CODES
VAPORS
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
FLUIDS
GASES
ISOTOPES
MATERIALS
MECHANICS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTORS
SAFETY
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents