CSPACE for a simulation of core damage progression during severe accidents
CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Safety and Performance Analysis CodE for nuclear pow...
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| Format: | Article |
| Language: | English |
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Elsevier
2021-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573321003867 |
| _version_ | 1819133786527367168 |
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| author | JinHo Song Dong-Gun Son JunHo Bae Sung Won Bae KwangSoon Ha Bub-Dong Chung YuJung Choi |
| author_facet | JinHo Song Dong-Gun Son JunHo Bae Sung Won Bae KwangSoon Ha Bub-Dong Chung YuJung Choi |
| author_sort | JinHo Song |
| collection | DOAJ |
| description | CSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Safety and Performance Analysis CodE for nuclear power plants) and core damage progression code of COMPASS (Core Meltdown Progression Accident Simulation Software). SPACE is responsible for the description of fluid state in nuclear system nodes, while COMPASS is responsible for the prediction of thermal and mechanical responses of core fuels and reactor vessel heat structures. New heat transfer models to each phase of the fluid, flow blockage, corium behavior in the lower head are added to COMPASS. Then, an interface module for the data transfer between two codes was developed to enable coupling. An implicit coupling scheme of wall heat transfer was applied to prevent fluid temperature oscillation. To validate the performance of newly developed code CSPACE, we analyzed typical severe accident scenarios for OPR1000 (Optimized Power Reactor 1000), which were initiated from large break loss of coolant accident, small break loss of coolant accident, and station black out accident. The results including thermal hydraulic behavior of RCS, core damage progression, hydrogen generation, corium behavior in the lower head, reactor vessel failure were reasonable and consistent. We demonstrate that CSPACE provides a good platform for the prediction of severe accident progression by detailed review of analysis results and a qualitative comparison with the results of previous MELCOR analysis. |
| first_indexed | 2024-12-22T09:52:50Z |
| format | Article |
| id | doaj.art-2a5e4a0fb2a145b3b6b63b198fecfbf7 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-22T09:52:50Z |
| publishDate | 2021-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-2a5e4a0fb2a145b3b6b63b198fecfbf72022-12-21T18:30:21ZengElsevierNuclear Engineering and Technology1738-57332021-12-01531239904002CSPACE for a simulation of core damage progression during severe accidentsJinHo Song0Dong-Gun Son1JunHo Bae2Sung Won Bae3KwangSoon Ha4Bub-Dong Chung5YuJung Choi6Korea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yusong-Gu, Daejon, 34057, South Korea; Corresponding author.Korea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yusong-Gu, Daejon, 34057, South KoreaKorea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yusong-Gu, Daejon, 34057, South KoreaKorea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yusong-Gu, Daejon, 34057, South KoreaKorea Atomic Energy Research Institute, 989-111 Daeduk-daero, Yusong-Gu, Daejon, 34057, South KoreaFNC Technology Co. Ltd. Heungdeok IT Valley Bldg. 32F, 13, Heungdeok 1-ro, Giheung-gu, Yongin-si, Gyeonggi-do, 16954, South KoreaCentral Research Institute, Korea Hydro and Nuclear Power Co.,LTd, 70, Yuseong-daero 1312-gil, Yusong-Gu, Daejon, 34101, South KoreaCSPACE (Core meltdown, Safety and Performance Analysis CodE for nuclear power plants) for a simulation of severe accident progression in a Pressurized Water Reactor (PWR) is developed by coupling of verified system thermal hydraulic code of SPACE (Safety and Performance Analysis CodE for nuclear power plants) and core damage progression code of COMPASS (Core Meltdown Progression Accident Simulation Software). SPACE is responsible for the description of fluid state in nuclear system nodes, while COMPASS is responsible for the prediction of thermal and mechanical responses of core fuels and reactor vessel heat structures. New heat transfer models to each phase of the fluid, flow blockage, corium behavior in the lower head are added to COMPASS. Then, an interface module for the data transfer between two codes was developed to enable coupling. An implicit coupling scheme of wall heat transfer was applied to prevent fluid temperature oscillation. To validate the performance of newly developed code CSPACE, we analyzed typical severe accident scenarios for OPR1000 (Optimized Power Reactor 1000), which were initiated from large break loss of coolant accident, small break loss of coolant accident, and station black out accident. The results including thermal hydraulic behavior of RCS, core damage progression, hydrogen generation, corium behavior in the lower head, reactor vessel failure were reasonable and consistent. We demonstrate that CSPACE provides a good platform for the prediction of severe accident progression by detailed review of analysis results and a qualitative comparison with the results of previous MELCOR analysis.http://www.sciencedirect.com/science/article/pii/S1738573321003867Severe accidentComputer codeCSPACESBOCore damage progressionCoupling |
| spellingShingle | JinHo Song Dong-Gun Son JunHo Bae Sung Won Bae KwangSoon Ha Bub-Dong Chung YuJung Choi CSPACE for a simulation of core damage progression during severe accidents Nuclear Engineering and Technology Severe accident Computer code CSPACE SBO Core damage progression Coupling |
| title | CSPACE for a simulation of core damage progression during severe accidents |
| title_full | CSPACE for a simulation of core damage progression during severe accidents |
| title_fullStr | CSPACE for a simulation of core damage progression during severe accidents |
| title_full_unstemmed | CSPACE for a simulation of core damage progression during severe accidents |
| title_short | CSPACE for a simulation of core damage progression during severe accidents |
| title_sort | cspace for a simulation of core damage progression during severe accidents |
| topic | Severe accident Computer code CSPACE SBO Core damage progression Coupling |
| url | http://www.sciencedirect.com/science/article/pii/S1738573321003867 |
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