Published February 25, 1999
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Experiments on Heat Removal in a Gap between Debris Crust and RPV Wall
Creators
- 1. Siemens AG/KWU, Freyeslebenstr. 1, 91058 Erlangen (Germany)
Description
The thermal hydraulic phenomena which occur in a gap between a debris crust and the RPV wall was investigated experimentally. The goal of these experiments was to find out the limits of heat removal at the relevant system parameters. For simulation of the decay heat a maximum heat flux of 550 kW/m2 was possible. The influence of gap width, water submersion, pressure and water subcooling on critical heat flux are presented. (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. 277-285
- 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
- 44026307
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; COOLING; CORIUM; HEAT FLUX; HEAT TRANSFER; PRESSURE DEPENDENCE; PRESSURE DROP; REACTOR ACCIDENTS; REACTOR CORES; REACTOR EXPERIMENTAL FACILITIES; REACTOR VESSELS; TEMPERATURE DEPENDENCE; THERMAL HYDRAULICS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; CONTAINMENT; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR COMPONENTS; REACTORS
Optional Information
- Notes
- 6 refs.