Uncertainty and Sensitivity Analysis of the Heat Transfer Mechanisms in the Lower Head
Creators
- 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit - GRS mbH, Forschungsgelaende, 85748 Garching (Germany)
Description
This paper illustrates a comprehensive approach to investigate the heat transfer mechanisms between relocated core debris and the RPV wall, to quantify the modelling uncertainties and to identify the most sensitive parameters or models involved. The investigations are mainly oriented to the TMI-2 conditions. Moreover, a high Rayleigh number scenario has been investigated. Previous simplified simulations with the thermohydraulic code ATHLET confirmed that a comparatively small coolant flow passing through a gap between lower crust and the vessel wall can reproduce the thermal history of the TMI-2 vessel during the accident. A refined integral model for the interaction between debris and RPV wall has been developed which covers the major physical phenomena governing the long-term integrity of the RPV. An uncertainty and sensitivity analysis of this model has been performed which accounts for modelling and parameter uncertainties. Quantitative sensitivity statements were derived for the code results accounting for the combined influence of these uncertainties as well as for the possible impact of the sampling error. (author)
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44026292.pdf
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the Workshop on in-vessel core debris retention and coolability
- Imprint Pagination
- 409 p.
- Journal Page Range
- p. 140-149
- Report number
- NEA-CSNI-R--1998-18
Conference
- Title
- Workshop on in-vessel core debris retention and coolability
- Dates
- 3-6 Mar 1998
- Place
- Garching (Germany)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 44026292
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ACCIDENT MANAGEMENT; ACCURACY; CONTAINMENT SYSTEMS; COOLANTS; CORE FLOODING SYSTEMS; CORIUM; DATA COVARIANCES; FLUID FLOW; HEAT TRANSFER; MATHEMATICAL MODELS; RAYLEIGH NUMBER; REACTOR ACCIDENTS; REACTOR CORES; REACTOR SAFETY; REACTOR VESSELS; SENSITIVITY ANALYSIS; THERMAL HYDRAULICS; THREE MILE ISLAND-2 REACTOR; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTAINMENT; DIMENSIONLESS NUMBERS; ECCS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; HYDRAULICS; MANAGEMENT; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs.