Technical bases and user's manual for the prototype of a Suppression Pool Aerosol Removal Code (SPARC)
This code was written to calculate the capture of aerosol particles in the pressure suppression pool (wet well) of a boiling water reactor under hypothetical accident conditions. The code incorporates five aerosol scrubbing models and two thermal-hydraulic models. The scrubbing models describe (1) steam condensation, (2) soluble particle growth in a humid atmosphere, (3) gravitational settling, (4) inertial deposition, (5) diffusional deposition. Mechanical entrainment of pool liquid by breaking of bubbles at the surface was also considered. An optional model for equilibrium pool temperature and a model for steam evaporation are the two thermal-hydraulic models used in the code. Steam evaporation was found to significantly retard deposition processes in pools near the boiling point. The code user supplies the values of several controlling variables in the code input. The SPARC output can include the decontamination factors (DF) of twenty different particle size groups, an overall DF for the whole particle distribution, particle log normal distribution parameters, and mass flow rates of particles (wet and dry) leaving the pool.
- Research Organization:
- Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5797428
- Report Number(s):
- NUREG/CR-3317; PNL-4742; ON: TI85013318
- Country of Publication:
- United States
- Language:
- English
Similar Records
User's manual for CONTAIN 1.1: A computer code for severe nuclear reactor accident containment analysis
User's manual for CONTAIN 1. 0, a computer code for severe nuclear reactor accident containment analysis
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
COMPUTER CODES
S CODES
RADIOACTIVE AEROSOLS
SCRUBBING
BUBBLES
MANUALS
PRESSURE SUPPRESSION
ACCIDENTS
AEROSOLS
COLLOIDS
DISPERSIONS
DOCUMENT TYPES
REACTORS
SOLS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled