Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs
Recent safety issues such as cladding oxidation and fuel fragmentation, relocation and dispersal (FFRD) make the loss-of-coolant accident (LOCA) acceptance criteria more difficult to be satisfied. To obtain the adequate safety margin and more economical use of the nuclear power plant, re-classificat...
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| Format: | Article |
| Language: | English |
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Elsevier
2025-01-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573324003887 |
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| author | Hae Min Park Jong Hyuk Lee Chiwoong Choi Kwi-Seok Ha Byung Hyun You Jaeseok Heo Kyung Doo Kim Sung Won Bae Seung Wook Lee Dong Hyuk Lee Sang Ik Lee Chan Eok Park Bub Dong Chung Kwang Won Seul |
| author_facet | Hae Min Park Jong Hyuk Lee Chiwoong Choi Kwi-Seok Ha Byung Hyun You Jaeseok Heo Kyung Doo Kim Sung Won Bae Seung Wook Lee Dong Hyuk Lee Sang Ik Lee Chan Eok Park Bub Dong Chung Kwang Won Seul |
| author_sort | Hae Min Park |
| collection | DOAJ |
| description | Recent safety issues such as cladding oxidation and fuel fragmentation, relocation and dispersal (FFRD) make the loss-of-coolant accident (LOCA) acceptance criteria more difficult to be satisfied. To obtain the adequate safety margin and more economical use of the nuclear power plant, re-classification of LOCAs for Korean operating PWRs is now under consideration to exclude the large break LOCA (LBLOCA) from the design basis accidents (DBAs). Therefore, the intermediate break LOCA (IBLOCA) might become the limiting break size of concern in the LOCA analysis. To accomplish this reform of LOCA classification, an extensive understanding of IBLOCA is crucial, and the applicability of safety analysis code should be confirmed. For this purpose, IBLOCA PIRT was developed. The PIRT panel was organized and the general process of the PIRT development established by Wilson and Boyack (1998) was adopted to develop the IBLOCA PIRT. Based on IBLOCA analyses using the safety and performance analyzing code (SPACE), the PIRT panel defined the temporal phases, systems, components and possible phenomena during an IBLOCA. For all possible phenomena, the relative importance and the knowledge level were determined for each component and each phase via discussions among PIRT panel members. For phenomena having relatively high importance, a code validation matrix was also developed. The results of the IBLOCA PIRT will be used to improve the SPACE code for IBLOCA application and resolve future regulatory issues. |
| format | Article |
| id | doaj-art-4ab0ffd6f0af46a5a87639f0c55baf64 |
| 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-4ab0ffd6f0af46a5a87639f0c55baf642025-01-12T05:24:36ZengElsevierNuclear Engineering and Technology1738-57332025-01-01571103141Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRsHae Min Park0Jong Hyuk Lee1Chiwoong Choi2Kwi-Seok Ha3Byung Hyun You4Jaeseok Heo5Kyung Doo Kim6Sung Won Bae7Seung Wook Lee8Dong Hyuk Lee9Sang Ik Lee10Chan Eok Park11Bub Dong Chung12Kwang Won Seul13Korea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKorea Atomic Energy Research Institute, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of Korea; Corresponding author.KHNP CRI, 70, 1312-gil, Yuseong-daero, Yuseong-gu, Daejeon, 34101, Republic of KoreaKEPCO NF., 242 Daedeok-daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaKEPCO E&C, 111, Daedeok-Daero 989 Beon-gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaFuture and Challenge Tech. Co. Ltd., Heungdeok1ro 13, Yeongdeok-dong, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, Republic of KoreaKorea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon, 34142, Republic of KoreaRecent safety issues such as cladding oxidation and fuel fragmentation, relocation and dispersal (FFRD) make the loss-of-coolant accident (LOCA) acceptance criteria more difficult to be satisfied. To obtain the adequate safety margin and more economical use of the nuclear power plant, re-classification of LOCAs for Korean operating PWRs is now under consideration to exclude the large break LOCA (LBLOCA) from the design basis accidents (DBAs). Therefore, the intermediate break LOCA (IBLOCA) might become the limiting break size of concern in the LOCA analysis. To accomplish this reform of LOCA classification, an extensive understanding of IBLOCA is crucial, and the applicability of safety analysis code should be confirmed. For this purpose, IBLOCA PIRT was developed. The PIRT panel was organized and the general process of the PIRT development established by Wilson and Boyack (1998) was adopted to develop the IBLOCA PIRT. Based on IBLOCA analyses using the safety and performance analyzing code (SPACE), the PIRT panel defined the temporal phases, systems, components and possible phenomena during an IBLOCA. For all possible phenomena, the relative importance and the knowledge level were determined for each component and each phase via discussions among PIRT panel members. For phenomena having relatively high importance, a code validation matrix was also developed. The results of the IBLOCA PIRT will be used to improve the SPACE code for IBLOCA application and resolve future regulatory issues.http://www.sciencedirect.com/science/article/pii/S1738573324003887Intermediate break loss-of-coolant accidentPIRTSPACE codeCode validation matrix |
| spellingShingle | Hae Min Park Jong Hyuk Lee Chiwoong Choi Kwi-Seok Ha Byung Hyun You Jaeseok Heo Kyung Doo Kim Sung Won Bae Seung Wook Lee Dong Hyuk Lee Sang Ik Lee Chan Eok Park Bub Dong Chung Kwang Won Seul Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs Nuclear Engineering and Technology Intermediate break loss-of-coolant accident PIRT SPACE code Code validation matrix |
| title | Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs |
| title_full | Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs |
| title_fullStr | Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs |
| title_full_unstemmed | Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs |
| title_short | Development of a phenomena identification and ranking table (PIRT) for intermediate break loss-of-coolant accident in PWRs |
| title_sort | development of a phenomena identification and ranking table pirt for intermediate break loss of coolant accident in pwrs |
| topic | Intermediate break loss-of-coolant accident PIRT SPACE code Code validation matrix |
| url | http://www.sciencedirect.com/science/article/pii/S1738573324003887 |
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