SPARC-90: A code for calculating fission product capture in suppression pools

Technical Report · Tue Oct 01 00:00:00 EDT 1991

DOI:https://doi.org/10.2172/6120360· OSTI ID:6120360

Owczarski, P C; Burk, K W ^[1]

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1. Pacific Northwest Lab., Richland, WA (United States)

This report describes the technical bases and use of two updated versions of a computer code initially developed to serve as a tool for calculating aerosol particle retention in boiling water reactor (BWR) pressure suppression pools during severe accidents, SPARC-87 and SPARC-90. The most recent version is SPARC-90. The initial or prototype version (Owczarski, Postma, and Schreck 1985) was improved to include the following: rigorous treatment of local particle deposition velocities on the surface of oblate spherical bubbles, new correlations for hydrodynamic behavior of bubble swarms, models for aerosol particle growth, both mechanistic and empirical models for vent exit region scrubbing, specific models for hydrodynamics of bubble breakup at various vent types, and models for capture of vapor iodine species. A complete user's guide is provided for SPARC-90 (along with SPARC-87). A code description, code operating instructions, partial code listing, examples of the use of SPARC-90, and summaries of experimental data comparison studies also support the use of SPARC-90. 29 refs., 4 figs., 11 tabs.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Div. of Regulatory Applications; Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6120360
• Report Number(s): NUREG/CR-5765; PNL-7723; ON: TI92003256
• Country of Publication: United States
• Language: English

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AEROSOLS
CONTAINMENT
BWR TYPE REACTORS
FISSION PRODUCT RELEASE
REACTOR ACCIDENTS
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COLLOIDS
COMPUTER CODES
DISPERSIONS
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
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MATERIALS
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RADIOACTIVE MATERIALS
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