Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400
Advanced ME (Mass and Energy) release analysis methodology and PT (Pressure and Temperature) analysis methodology were developed using advanced thermal-hydraulic computer codes of three-field model for the Gen-III reactor, APR1400. Both conservative and realistic approaches were harmoniously adopted...
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| Format: | Article |
| Language: | English |
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Elsevier
2025-09-01
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| Series: | Nuclear Engineering and Technology |
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| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573325001846 |
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| author | Seong-ho Jee Yong-Ju Cho Kum-Ho Han Jisu Kim Sung-yong Kim Je-woo Cho Jehee Lee Yeon-Jun Choo Jeong-ju Kim Chan-eok Park Seok-jeong Park Sun-Hong Yoon Soon-Joon Hong |
| author_facet | Seong-ho Jee Yong-Ju Cho Kum-Ho Han Jisu Kim Sung-yong Kim Je-woo Cho Jehee Lee Yeon-Jun Choo Jeong-ju Kim Chan-eok Park Seok-jeong Park Sun-Hong Yoon Soon-Joon Hong |
| author_sort | Seong-ho Jee |
| collection | DOAJ |
| description | Advanced ME (Mass and Energy) release analysis methodology and PT (Pressure and Temperature) analysis methodology were developed using advanced thermal-hydraulic computer codes of three-field model for the Gen-III reactor, APR1400. Both conservative and realistic approaches were harmoniously adopted for the ease of licensing and for economics. Conservative approach was taken for the ambiguous process and phenomena, while realistic approach for the clearly identified process and phenomena. Break separation model was implemented in the ME analysis step for conservatism, and direct spillage was bypassed considering the APR1400 features. Reactor–containment coupling analysis was introduced in ME analysis for realistic analysis. Liquid carryover rate was determined by assessing the typical experiments. For PT analysis several mechanistic models including water surface evaporation and condensation model were developed. And these new models evaluated the conventional models. Unrecovered water modelling was introduced, and realistic component arrangement was modeled. This new ME and PT methodology result in additional design pressure margin of nearly 66 kPa. |
| format | Article |
| id | doaj-art-68511d4e7d8a4bf28f88b4a6d39d291b |
| institution | Kabale University |
| issn | 1738-5733 |
| language | English |
| publishDate | 2025-09-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj-art-68511d4e7d8a4bf28f88b4a6d39d291b2025-08-20T03:48:13ZengElsevierNuclear Engineering and Technology1738-57332025-09-0157910361610.1016/j.net.2025.103616Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400Seong-ho Jee0Yong-Ju Cho1Kum-Ho Han2Jisu Kim3Sung-yong Kim4Je-woo Cho5Jehee Lee6Yeon-Jun Choo7Jeong-ju Kim8Chan-eok Park9Seok-jeong Park10Sun-Hong Yoon11Soon-Joon Hong12Safety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Research Team, KEPCO Engineering & Construction Co. Inc., Gimcheon-si, Kyungsangbuk-do, 39660, Republic of KoreaFNC Tech. Co. Ltd., Floor 32, Heungdeok IT Valley, 13 Heungdeok 1-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaFNC Tech. Co. Ltd., Floor 32, Heungdeok IT Valley, 13 Heungdeok 1-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, Republic of KoreaFNC Tech. Co. Ltd., Floor 32, Heungdeok IT Valley, 13 Heungdeok 1-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Analysis Department, KEPCO E&C Company Inc., 111, Daedeok-daero 989 Beon-Gil, Yuseong-gu, Daejeon, 34057, Republic of KoreaSafety Research Team, KEPCO Engineering & Construction Co. Inc., Gimcheon-si, Kyungsangbuk-do, 39660, Republic of KoreaFNC Tech. Co. Ltd., Floor 32, Heungdeok IT Valley, 13 Heungdeok 1-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, Republic of Korea; Corresponding author.Advanced ME (Mass and Energy) release analysis methodology and PT (Pressure and Temperature) analysis methodology were developed using advanced thermal-hydraulic computer codes of three-field model for the Gen-III reactor, APR1400. Both conservative and realistic approaches were harmoniously adopted for the ease of licensing and for economics. Conservative approach was taken for the ambiguous process and phenomena, while realistic approach for the clearly identified process and phenomena. Break separation model was implemented in the ME analysis step for conservatism, and direct spillage was bypassed considering the APR1400 features. Reactor–containment coupling analysis was introduced in ME analysis for realistic analysis. Liquid carryover rate was determined by assessing the typical experiments. For PT analysis several mechanistic models including water surface evaporation and condensation model were developed. And these new models evaluated the conventional models. Unrecovered water modelling was introduced, and realistic component arrangement was modeled. This new ME and PT methodology result in additional design pressure margin of nearly 66 kPa.http://www.sciencedirect.com/science/article/pii/S1738573325001846Mass and energyPressure and temperatureCode development and couplingLoss of coolant accidentMain steam line break |
| spellingShingle | Seong-ho Jee Yong-Ju Cho Kum-Ho Han Jisu Kim Sung-yong Kim Je-woo Cho Jehee Lee Yeon-Jun Choo Jeong-ju Kim Chan-eok Park Seok-jeong Park Sun-Hong Yoon Soon-Joon Hong Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 Nuclear Engineering and Technology Mass and energy Pressure and temperature Code development and coupling Loss of coolant accident Main steam line break |
| title | Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 |
| title_full | Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 |
| title_fullStr | Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 |
| title_full_unstemmed | Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 |
| title_short | Development of advanced containment thermal-hydraulic analysis methodology based on three-field model codes for APR1400 |
| title_sort | development of advanced containment thermal hydraulic analysis methodology based on three field model codes for apr1400 |
| topic | Mass and energy Pressure and temperature Code development and coupling Loss of coolant accident Main steam line break |
| url | http://www.sciencedirect.com/science/article/pii/S1738573325001846 |
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