Numerical Investigation of Turbulent Natural Convection Heat Transfer in an Internally-Heated Melt Pool and Metallic Layer
- 1. Division of Nuclear Power Safety, Royal Institute of Technology, Brinellvigen 60, 10044 Stockholm (Sweden)
Description
This paper presents results of numerical investigation of turbulent natural convection in an internally-heated oxidic pool, and in a metallic layer heated from below and cooled from top and sidewalls. Emphasis is placed upon applicability of the existing heat transfer correlations (obtained from simulant-material experiments) in assessments of a prototypic severe reactor accident. The objectives of this study are (i) to improve the current understanding of the physics of unstably stratified flows, and (ii) to reduce uncertainties associated with modeling and assessment of natural convection heat transfer in the above configuration. Prediction capabilities of different turbulence modeling approaches are first examined and discussed, based on extensive results of numerical investigations performed by present authors. Findings from numerical modeling of turbulent natural convection flow and heat transfer in melt pools and metallic layers are then described. (authors)
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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. 207-214
- 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
- 44026299
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; ACCURACY; COMPUTERIZED SIMULATION; CONTAINMENT SYSTEMS; CORE FLOODING SYSTEMS; CORIUM; DATA COVARIANCES; HEAT TRANSFER; K CODES; MATHEMATICAL MODELS; MELTING; NATURAL CONVECTION; REACTOR ACCIDENTS; REACTOR CORES; REACTOR VESSELS; STRATIFICATION; THERMAL HYDRAULICS; TURBULENT FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTAINMENT; CONVECTION; ECCS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID FLOW; FLUID MECHANICS; HEAT TRANSFER; HYDRAULICS; MANAGEMENT; MASS TRANSFER; MECHANICS; PHASE TRANSFORMATIONS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; SIMULATION
Optional Information
- Notes
- 18efs.