A Monte Carlo method for estimation of the probability of combustion-induced containment failure
Creators
- 1. Energy Research, Inc. P.O. Box 2034 Rockville, Maryland 20847-2034 (United States)
Description
The paper will present a probabilistic approach to assessment of the likelihood of containment failure due to combustion of hydrogen and carbon monoxide using a Monte Carlo method. The analyses are performed within an event tree framework that considers three phases: (i) Phase 1 - extends from start of the accident (or alternatively, from the onset of rapid Zircaloy oxidation) up until the time of reactor coolant system (RCS) or reactor pressure vessel (RPV) breach (period prior to RCS/RPV breach); (ii) Phase 2 - corresponds to RCS/RPV breach period; and (iii) Phase 3 - corresponds to the period following Phase 2 and Molten Core Concrete Interaction (MCCI) and during the period that containment conditions would be conducive (i.e., not steam-inerted) to combustion. For each phase, the likelihood of combustion-induced containment failure is decomposed in order to enable a logical and consistent quantification. In this treatment, the conditional probability of containment failure in each subsequent phase is directly dependent on the existence of ignition sources and flammability in the prior phase (or phases). Therefore, for those event tree paths on which prior combustion events have taken place, a substantially smaller hydrogen mass will be available for a later combustion (note that the combustion of CO is only applicable to Phase 3). On the other hands, for event tree paths that involved no prior combustion events, a larger quantity of hydrogen could be available for later combustion. Table 1 lists a summary of estimated conditional containment failure probabilities for Westinghouse PWRs with large-dry containment, during various phases of severe accidents. It is seen that the overall probability of early and very early containment failure is estimated to be essentially zero for all Westinghouse plants with large-dry containment. On the other hand, the likelihood of late containment failure due to combustion is estimated to range from negligibly low values for sub-atmospheric designs to as high as about 0.1 for some of the atmospheric plants. (authors)
Availability note (English)
Available from INIS in electronic formFiles
36055623.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 1 p.
- Report number
- INIS-FR--3546
Conference
- Title
- 11. international topical meeting on nuclear reactor thermal hydraulics (Nureth 11)
- Dates
- 2-6 Oct 2005
- Place
- Avignon (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 36055623
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON MONOXIDE; COMBUSTION; CONCRETES; CONTAINMENT BUILDINGS; CONTAINMENT SPRAY SYSTEMS; FAILURE MODE ANALYSIS; FLAMMABILITY; HYDROGEN; MELTDOWN; MONTE CARLO METHOD; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; BUILDINGS; CALCULATION METHODS; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; CHEMICAL REACTIONS; COMBUSTION PROPERTIES; CONTAINERS; CONTAINMENT; CONTAINMENT SYSTEMS; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MATERIALS; NONMETALS; OXIDATION; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; THERMOCHEMICAL PROCESSES; WATER COOLED REACTORS; WATER MODERATED REACTORS