The response of BWR Mark II containments to station blackout severe accident sequences

Technical Report · Wed May 01 00:00:00 EDT 1991

OSTI ID:5535558

Greene, S R; Hodge, S A; Hyman, C R; Tobias, M L ^[1]

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1. Oak Ridge National Lab., TN (USA)

This report describes the results of a series of calculations conducted to investigate the response of BWR Mark 2 containments to short-term and long-term station blackout severe accident sequences. The BWR-LTAS, BWRSAR, and MELCOR codes were employed to conduct quantitative accident sequence progression and containment response analyses for several station blackout scenarios. The accident mitigation effectiveness of automatic depressurization system actuation, drywell flooding via containment spray operation, and debris quenching in Mark 2 suppression pools is assessed. 27 refs., 16 figs., 21 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Safety Issue Resolution; Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USNRC; Nuclear Regulatory Commission, Washington, DC (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5535558
• Report Number(s): NUREG/CR-5565; ORNL/TM-11548; ON: TI91013929; TRN: 91-019095
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
CONTAINMENT
B CODES
M CODES
BLACKOUTS
DEPRESSURIZATION SYSTEMS
EVALUATION
MITIGATION
PRESSURE SUPPRESSION
ACCIDENTS
COMPUTER CODES
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled