Radionuclide release calculations for selected severe accident scenarios. PWR, ice condenser design. Volume 2

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

OSTI ID:5593067

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 pressurized water reactor with an ice-condenser 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 Sequoyah plant has been used in this study as an example of a PWR ice-condenser plant.

• Research Organization: Battelle Columbus Div., OH (USA)
• OSTI ID: 5593067
• Report Number(s): NUREG/CR-4624-Vol.2; BMI-2139-Vol.2; ON: TI86901593
• Country of Publication: United States
• Language: English

Related Subjects

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Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
500300 -- Environment
Atmospheric-- Radioactive Materials Monitoring & Transport-- (-1989)
54 ENVIRONMENTAL SCIENCES
ACCIDENTS
COMPUTERIZED SIMULATION
CONTAINMENT
ENVIRONMENTAL TRANSPORT
FISSION PRODUCT RELEASE
MASS TRANSFER
PWR TYPE REACTORS
RADIATION ACCIDENTS
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
REACTORS
SIMULATION
WATER COOLED REACTORS
WATER MODERATED REACTORS