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Title: Application of the CFD CONV code to the analysis of LIVE L6 test

Abstract

The thermo-physical behaviour of a corium pool in reactor pressure vessel of a pressurised water reactor is of principal importance for the prediction of core melt down accident development. This concerns, in general, the understanding of a severe accident with core melting, its course, major critical phases and timing, and the influence of these processes on the accident progression in terms of assessing the possibility to remove the released heat by external vessel cooling. The general objective of the LIVE program at KIT is to study phenomena resulting from core melting experimentally in large-scale 3D geometry with emphasis on the transient behaviour. The presented paper describes analysis and interpretation of the LIVE L6 experiment, in which the molten pool (non-eutectic melt KNO{sub 3}-NaNO{sub 3}) was separated by horizontal copper plate in order to develop the approach to the analysis of layering and focusing effects as the most challenging factors. (authors)

Authors:
; ;  [1];  [2]
  1. Karlsruhe Inst. of Technology, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany)
  2. IBRAE Nuclear Safety Inst., B.Tulskaya 52, 115191, Moscow (Russian Federation)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
22107842
Resource Type:
Conference
Resource Relation:
Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 20 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COMPUTER CODES; COOLING; COPPER; EUTECTICS; FLUID MECHANICS; FORECASTING; GEOMETRY; HEAT; MELTING; NUCLEAR POWER PLANTS; POTASSIUM NITRATES; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; SODIUM NITRATES; WATER

Citation Formats

Palagin, A., Kretzschmar, F., Miassoedov, A., and Chudanov, V. Application of the CFD CONV code to the analysis of LIVE L6 test. United States: N. p., 2012. Web.
Palagin, A., Kretzschmar, F., Miassoedov, A., & Chudanov, V. Application of the CFD CONV code to the analysis of LIVE L6 test. United States.
Palagin, A., Kretzschmar, F., Miassoedov, A., and Chudanov, V. Sun . "Application of the CFD CONV code to the analysis of LIVE L6 test". United States.
@article{osti_22107842,
title = {Application of the CFD CONV code to the analysis of LIVE L6 test},
author = {Palagin, A. and Kretzschmar, F. and Miassoedov, A. and Chudanov, V.},
abstractNote = {The thermo-physical behaviour of a corium pool in reactor pressure vessel of a pressurised water reactor is of principal importance for the prediction of core melt down accident development. This concerns, in general, the understanding of a severe accident with core melting, its course, major critical phases and timing, and the influence of these processes on the accident progression in terms of assessing the possibility to remove the released heat by external vessel cooling. The general objective of the LIVE program at KIT is to study phenomena resulting from core melting experimentally in large-scale 3D geometry with emphasis on the transient behaviour. The presented paper describes analysis and interpretation of the LIVE L6 experiment, in which the molten pool (non-eutectic melt KNO{sub 3}-NaNO{sub 3}) was separated by horizontal copper plate in order to develop the approach to the analysis of layering and focusing effects as the most challenging factors. (authors)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2012},
month = {7}
}

Conference:
Other availability
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