Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events

The present study focuses on the development of an equipment qualification (EQ) testing facility for Class 1E equipment in nuclear power plants (NPPs), emphasizing the need to ensure safety functions under design basis events (DBEs). The Republic of Korea (ROK) has implemented international safety s...

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Main Authors: Kyungha Ryu, Seonggyu Cho, Taeho Roh, Sangkyo Kim, Taekook Park, Taehyun Lee, Jongwon Park, Jaehyun Cho
Format: Article
Language:English
Published: Elsevier 2025-01-01
Series:Nuclear Engineering and Technology
Subjects:
Online Access:http://www.sciencedirect.com/science/article/pii/S1738573324003747
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author Kyungha Ryu
Seonggyu Cho
Taeho Roh
Sangkyo Kim
Taekook Park
Taehyun Lee
Jongwon Park
Jaehyun Cho
author_facet Kyungha Ryu
Seonggyu Cho
Taeho Roh
Sangkyo Kim
Taekook Park
Taehyun Lee
Jongwon Park
Jaehyun Cho
author_sort Kyungha Ryu
collection DOAJ
description The present study focuses on the development of an equipment qualification (EQ) testing facility for Class 1E equipment in nuclear power plants (NPPs), emphasizing the need to ensure safety functions under design basis events (DBEs). The Republic of Korea (ROK) has implemented international safety standards to support large NPP projects, necessitating the development of domestic EQ testing facilities to reduce the dependence on foreign facilities. To address this need, herein, a specialized facility capable of simulating harsh DBE conditions that may occur in NPPs in ROK was constructed. Through exhaustive research, target temperature and pressure profiles were developed for pressurized water reactors, and a superheated steam injection technique was devised for rapid temperature and pressure changes. The present study contributes to the advancement of domestic EQ testing capabilities, achieving up to 230 °C and 700 kPa within 30 s.
format Article
id doaj-art-d8b9dd31212242cbb468413c697727ee
institution Kabale University
issn 1738-5733
language English
publishDate 2025-01-01
publisher Elsevier
record_format Article
series Nuclear Engineering and Technology
spelling doaj-art-d8b9dd31212242cbb468413c697727ee2025-01-12T05:24:34ZengElsevierNuclear Engineering and Technology1738-57332025-01-01571103127Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis eventsKyungha Ryu0Seonggyu Cho1Taeho Roh2Sangkyo Kim3Taekook Park4Taehyun Lee5Jongwon Park6Jaehyun Cho7Korea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaKorea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaSchool of Energy Systems Engineering, Chung-Ang University, 84 Heukseok-ro, Dongjak-gu, Seoul, 06974, Republic of KoreaKorea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaKorea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaKorea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaKorea Institute of Machinery & Materials, 156 Gajeongbuk-Ro, Yuseong-Gu, Daejeon, 34103, Republic of KoreaSchool of Energy Systems Engineering, Chung-Ang University, 84 Heukseok-ro, Dongjak-gu, Seoul, 06974, Republic of Korea; Corresponding author.The present study focuses on the development of an equipment qualification (EQ) testing facility for Class 1E equipment in nuclear power plants (NPPs), emphasizing the need to ensure safety functions under design basis events (DBEs). The Republic of Korea (ROK) has implemented international safety standards to support large NPP projects, necessitating the development of domestic EQ testing facilities to reduce the dependence on foreign facilities. To address this need, herein, a specialized facility capable of simulating harsh DBE conditions that may occur in NPPs in ROK was constructed. Through exhaustive research, target temperature and pressure profiles were developed for pressurized water reactors, and a superheated steam injection technique was devised for rapid temperature and pressure changes. The present study contributes to the advancement of domestic EQ testing capabilities, achieving up to 230 °C and 700 kPa within 30 s.http://www.sciencedirect.com/science/article/pii/S1738573324003747Equipment qualificationDesign based eventLoss of coolant accidentClass 1ESuperheated steam
spellingShingle Kyungha Ryu
Seonggyu Cho
Taeho Roh
Sangkyo Kim
Taekook Park
Taehyun Lee
Jongwon Park
Jaehyun Cho
Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
Nuclear Engineering and Technology
Equipment qualification
Design based event
Loss of coolant accident
Class 1E
Superheated steam
title Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
title_full Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
title_fullStr Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
title_full_unstemmed Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
title_short Enhancing equipment qualification testing facility for nuclear power plants: Achieving rapid temperature and pressure increase during design basis events
title_sort enhancing equipment qualification testing facility for nuclear power plants achieving rapid temperature and pressure increase during design basis events
topic Equipment qualification
Design based event
Loss of coolant accident
Class 1E
Superheated steam
url http://www.sciencedirect.com/science/article/pii/S1738573324003747
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