Radionuclide release calculations for selected severe accident scenarios. Volume 4. BWR, Mark III design

Technical Report · Tue Jul 01 04:00:00 EDT 1986

OSTI ID:5507335

Denning, R S; Gieseke, J A; Cybulskis, P; Lee, K W; Jordan, H; Curtis, L A; Kelly, R F; Kogan, V; Schumacher, P M

This report presents results of analyses of the environmental releases of fission products (source terms) for severe accident scenarios in a boiling water reactor with a Mark III containment. The analyses were performed to support the Severe Accident Risk Reduction/Risk Rebaselining Program (SARRP) which is being undertaken for the US Nuclear Regulatory Commission by Sandia National Laboratories. In the SARRP program, risk estimates are being generated for a number of reference plant designs. The Grand Gulf plant has been used in this study as an example of a Mark III plant.

• Research Organization: Battelle Columbus Div., OH (USA)
• OSTI ID: 5507335
• Report Number(s): NUREG/CR-4624-Vol.4; BMI-2139-Vol.4; ON: TI86901590
• Country of Publication: United States
• Language: English

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54 ENVIRONMENTAL SCIENCES
ACCIDENTS
BWR TYPE REACTORS
COMPUTERIZED SIMULATION
CONTAINMENT
ENVIRONMENTAL TRANSPORT
FISSION PRODUCT RELEASE
MASS TRANSFER
RADIATION ACCIDENTS
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS