Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant

A Spent Fuel Pool (SFP) is designed to store spent fuel assemblies in the pool. And, a SFP cooling and cleanup system cools the SFP coolant through a heat exchanger which exchanges heat with component cooling water. If the cooling system fails or interfacing pipe (e.g., suction or discharge pipe) br...

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Main Authors: Jintae Choi, Ho Seok
Format: Article
Language:English
Published: Elsevier 2021-04-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573320308731
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spelling doaj-90be55fca66a481e8d11a7f163dd09c92021-04-02T04:49:04ZengElsevierNuclear Engineering and Technology1738-57332021-04-0153411271133Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plantJintae Choi0Ho Seok1Corresponding author.; KEPCO E&C, 269 Hyeoksin-ro, Gimcheon-si, Gyeongsangbuk-do, 39660, Republic of KoreaKEPCO E&C, 269 Hyeoksin-ro, Gimcheon-si, Gyeongsangbuk-do, 39660, Republic of KoreaA Spent Fuel Pool (SFP) is designed to store spent fuel assemblies in the pool. And, a SFP cooling and cleanup system cools the SFP coolant through a heat exchanger which exchanges heat with component cooling water. If the cooling system fails or interfacing pipe (e.g., suction or discharge pipe) breaks, the cooling function may be lost, probably leading to fuel damage. In order to prevent such an incident, it is required to properly cool the spent fuel assemblies in the SFP by either recovering the cooling system or injecting water into the SFP. Probabilistic safety assessment (PSA) is a good tool to assess the SFP risk when an initiating event for the SFP occurs. Since PSA has been focused on reactor-side so far, it is required to study on the framework of PSA approach for SFP and identify the key factors in terms of fuel damage frequency (FDF) through a case study. In this study, therefore, a case study of SFP-PSA on the basis of design information of APR-1400 has been conducted quantitatively, and several sensitivity analyses have been conducted to understand the impact of the key factors on FDF.http://www.sciencedirect.com/science/article/pii/S1738573320308731Probabilistic safety assessmentProbabilistic risk assessmentSpent fuel pool
collection DOAJ
language English
format Article
sources DOAJ
author Jintae Choi
Ho Seok
spellingShingle Jintae Choi
Ho Seok
Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
Nuclear Engineering and Technology
Probabilistic safety assessment
Probabilistic risk assessment
Spent fuel pool
author_facet Jintae Choi
Ho Seok
author_sort Jintae Choi
title Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
title_short Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
title_full Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
title_fullStr Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
title_full_unstemmed Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
title_sort development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant
publisher Elsevier
series Nuclear Engineering and Technology
issn 1738-5733
publishDate 2021-04-01
description A Spent Fuel Pool (SFP) is designed to store spent fuel assemblies in the pool. And, a SFP cooling and cleanup system cools the SFP coolant through a heat exchanger which exchanges heat with component cooling water. If the cooling system fails or interfacing pipe (e.g., suction or discharge pipe) breaks, the cooling function may be lost, probably leading to fuel damage. In order to prevent such an incident, it is required to properly cool the spent fuel assemblies in the SFP by either recovering the cooling system or injecting water into the SFP. Probabilistic safety assessment (PSA) is a good tool to assess the SFP risk when an initiating event for the SFP occurs. Since PSA has been focused on reactor-side so far, it is required to study on the framework of PSA approach for SFP and identify the key factors in terms of fuel damage frequency (FDF) through a case study. In this study, therefore, a case study of SFP-PSA on the basis of design information of APR-1400 has been conducted quantitatively, and several sensitivity analyses have been conducted to understand the impact of the key factors on FDF.
topic Probabilistic safety assessment
Probabilistic risk assessment
Spent fuel pool
url http://www.sciencedirect.com/science/article/pii/S1738573320308731
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