Source term attenuation by water in the Mark I boiling water reactor drywell
- Sandia National Labs., Albuquerque, NM (United States)
Mechanistic models of aerosol decontamination by an overlying water pool during core debris/concrete interactions and spray removal of aerosols from a Mark I drywell atmosphere are developed. Eighteen uncertain features of the pool decontamination model and 19 uncertain features of the model for the rate coefficient of spray removal of aerosols are identified. Ranges for values of parameters that characterize these uncertain features of the models are established. Probability density functions for values within these ranges are assigned according to a set of rules. A Monte Carlo uncertainty analysis of the decontamination factor produced by water pools 30 and 50 cm deep and subcooled 0--70 K is performed. An uncertainty analysis for the rate constant of spray removal of aerosols is done for water fluxes of 0.25, 0.01, and 0.001 cm{sup 3} H{sub 2}O/cm{sup 2}-s and decontamination factors of 1.1, 2, 3.3, 10, 100, and 1000.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10186838
- Report Number(s):
- NUREG/CR-5978; SAND-92-2688; ON: TI94001301; TRN: 93:025511
- Resource Relation:
- Other Information: PBD: Sep 1993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
SPRAYS
SOURCE TERMS
PONDS
AEROSOLS
DECONTAMINATION
CORIUM
CONCRETES
INTERACTIONS
DATA COVARIANCES
SAMPLING
MATHEMATICAL MODELS
REACTOR SAFETY
HEAT TRANSFER
HYDRAULICS
ATTENUATION
220900
210100
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED