Modelling of the MCCI phenomena with the presence of a water layer
- 1. Mechanical and Nuclear Engineering Dept., Univ. of Wisconsin, Madison, WI (United States)
- 2. Nuclear Div., Electric Power Research Inst., Palo Alto, CA (United States)
Description
If a severe reactor accident progresses to the point that the core melt breaches the reactor pressure vessel, the core is deposited onto the containment concrete basemat. Termination of the accident and attainment of a stable state where core cooling is assured requires the presence of a water layer which carries away nuclear decay heat. This paper discusses the possible set of conditions necessary for the attainment of this state and presents a simple thermal-structural model that predicts the transition of the molten core-concrete interaction from one state to the other. Such a model provides a semi-quantitative picture of how the interaction may proceed and how it scales from tests to prototypic reactor scale. All quantitative predictions are tentative pending more exact core-concrete properties. (orig.)
Additional details
Publishing Information
- Imprint Title
- Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions
- Imprint Pagination
- 603 p.
- Journal Page Range
- p. 435-454.
- ISSN
- 0303-4003
- Report number
- KFK--5108
Conference
- Title
- 2. OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions.
- Dates
- 1-3 Apr 1992.
- Place
- Karlsruhe (Germany).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 25034325
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONCRETES; CONTAINMENT; COOLING; MATHEMATICAL MODELS; MELTDOWN; PWR TYPE REACTORS; WATER
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; MATERIALS; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOVAL; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- NEA/CSNI/R--(92)10.