A framework for the assessment of severe accident management strategies

Technical Report · Wed Sep 01 04:00:00 EDT 1993

DOI:https://doi.org/10.2172/10187578· OSTI ID:10187578

Kastenberg, W E ^[1]; Apostolakis, G; Dhir, V K ^[2]

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1. ed.
2. California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering; and others

Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• OSTI ID: 10187578
• Report Number(s): NUREG/CR--6056; ON: TI94000586
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
DIAGRAMS
FAILURE MODE ANALYSIS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
MANAGEMENT
MELTDOWN
MITIGATION
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PROBABILITY
PWR TYPE REACTORS
REACTOR SAFETY
RISK ASSESSMENT