Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant

This paper illustrates the application of a severe accident analysis computer program to the uncertainty analysis of molten corium-concrete interaction (MCCI) phenomena in cases of severe accidents in CANDU6 type plant. The potential hazard of MCCI is a failure of the reactor building owing to the p...

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Main Authors: Sooyong Park, Kwang-Il Ahn, YongMann Song
Format: Article
Language:English
Published: Wiley 2015-01-01
Series:Science and Technology of Nuclear Installations
Online Access:http://dx.doi.org/10.1155/2015/462941
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author Sooyong Park
Kwang-Il Ahn
YongMann Song
author_facet Sooyong Park
Kwang-Il Ahn
YongMann Song
author_sort Sooyong Park
collection DOAJ
description This paper illustrates the application of a severe accident analysis computer program to the uncertainty analysis of molten corium-concrete interaction (MCCI) phenomena in cases of severe accidents in CANDU6 type plant. The potential hazard of MCCI is a failure of the reactor building owing to the possibility of a calandria vault floor melt-through even though the containment filtered vent system is operated. Meanwhile, the MCCI still has large uncertainties in several phenomena such as a melt spreading area and the extent of water ingression into a continuous debris layer. The purpose of this study is to evaluate the MCCI in the calandria vault floor via an uncertainty analysis using the ISAAC program for the CANDU6.
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institution Kabale University
issn 1687-6075
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language English
publishDate 2015-01-01
publisher Wiley
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series Science and Technology of Nuclear Installations
spelling doaj-art-4a4f9bbcdb734592baedb43cfd4448c42025-02-03T05:46:25ZengWileyScience and Technology of Nuclear Installations1687-60751687-60832015-01-01201510.1155/2015/462941462941Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 PlantSooyong Park0Kwang-Il Ahn1YongMann Song2Korea Atomic Energy Research Institute, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daejeon 305-353, Republic of KoreaKorea Atomic Energy Research Institute, Daejeon 305-353, Republic of KoreaThis paper illustrates the application of a severe accident analysis computer program to the uncertainty analysis of molten corium-concrete interaction (MCCI) phenomena in cases of severe accidents in CANDU6 type plant. The potential hazard of MCCI is a failure of the reactor building owing to the possibility of a calandria vault floor melt-through even though the containment filtered vent system is operated. Meanwhile, the MCCI still has large uncertainties in several phenomena such as a melt spreading area and the extent of water ingression into a continuous debris layer. The purpose of this study is to evaluate the MCCI in the calandria vault floor via an uncertainty analysis using the ISAAC program for the CANDU6.http://dx.doi.org/10.1155/2015/462941
spellingShingle Sooyong Park
Kwang-Il Ahn
YongMann Song
Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
Science and Technology of Nuclear Installations
title Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
title_full Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
title_fullStr Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
title_full_unstemmed Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
title_short Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant
title_sort uncertainty analysis of the potential hazard of mcci during severe accidents for the candu6 plant
url http://dx.doi.org/10.1155/2015/462941
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AT kwangilahn uncertaintyanalysisofthepotentialhazardofmcciduringsevereaccidentsforthecandu6plant
AT yongmannsong uncertaintyanalysisofthepotentialhazardofmcciduringsevereaccidentsforthecandu6plant