A Review on Analysis of LWR Severe AccidentSource: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 004::page 41018DOI: 10.1115/1.4030364Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: A severe accident (SA) is defined as an incident involving melting of the nuclear reactor core and the release of fission products (FP) from the fuel and their associated risks. In the SA, the containment may fail, causing the public hazard of fission products released to the environment. This review elaborates the resolved issues of SAs under the condition of a hypothetical SA. SA research that has been performed over the years is briefly described, including various SA scenarios. The SA scenarios involve core melt scenarios from the beginning of core degradation to melt formation and relocation into the lower head and to the containment, the interactions of the molten corium with water and concrete, the behavior of fission products inand exvessel, hydrogenrelated phenomena, and all associated risks. The mitigation strategies that have been adopted in existing reactors and advanced light water reactors (ALWR) are also discussed. These mitigation measures can keep the reactor vessel or containment intact and terminate the SA progression. SA analysis codes are then summarized and divided into three categories, namely, systematic analysis codes, mechanism analysis codes, and singlefunction analysis codes. Next, the unresolved issues of SAs are proposed, including narrow gap cooling, melt chemical interactions, steam explosion loads, molten debris coolability, and iodine chemistry. Further experimental and theoretical research activities should be conducted to resolve these issues; consequently, some recommendations for further research work are also given in the last part of this review. This review aims to add to the knowledge and understanding of SA research in the past few decades and to benefit further research of SAs.
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contributor author | Zhang, Y. P. | |
contributor author | Niu, S. P. | |
contributor author | Zhang, L. T. | |
contributor author | Qiu, S. Z. | |
contributor author | Su, G. H. | |
contributor author | Tian, W. X. | |
date accessioned | 2017-05-09T01:22:31Z | |
date available | 2017-05-09T01:22:31Z | |
date issued | 2015 | |
identifier issn | 2332-8983 | |
identifier other | NERS_1_4_041018.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl/handle/yetl/159328 | |
description abstract | A severe accident (SA) is defined as an incident involving melting of the nuclear reactor core and the release of fission products (FP) from the fuel and their associated risks. In the SA, the containment may fail, causing the public hazard of fission products released to the environment. This review elaborates the resolved issues of SAs under the condition of a hypothetical SA. SA research that has been performed over the years is briefly described, including various SA scenarios. The SA scenarios involve core melt scenarios from the beginning of core degradation to melt formation and relocation into the lower head and to the containment, the interactions of the molten corium with water and concrete, the behavior of fission products inand exvessel, hydrogenrelated phenomena, and all associated risks. The mitigation strategies that have been adopted in existing reactors and advanced light water reactors (ALWR) are also discussed. These mitigation measures can keep the reactor vessel or containment intact and terminate the SA progression. SA analysis codes are then summarized and divided into three categories, namely, systematic analysis codes, mechanism analysis codes, and singlefunction analysis codes. Next, the unresolved issues of SAs are proposed, including narrow gap cooling, melt chemical interactions, steam explosion loads, molten debris coolability, and iodine chemistry. Further experimental and theoretical research activities should be conducted to resolve these issues; consequently, some recommendations for further research work are also given in the last part of this review. This review aims to add to the knowledge and understanding of SA research in the past few decades and to benefit further research of SAs. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | A Review on Analysis of LWR Severe Accident | |
type | Journal Paper | |
journal volume | 1 | |
journal issue | 4 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4030364 | |
journal fristpage | 41018 | |
journal lastpage | 41018 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 004 | |
contenttype | Fulltext |