Numerical assessment of LOCA experiments of RD-14M using MARS-KS code
The code assessment on the design basis events has been of fundamental importance to the safety analyses of the nuclear power plants. When a system analysis code is released to the new version by improving the existing models and correcting the found errors, it is essential to make sure that the upd...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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KeAi Communications Co., Ltd.
2020-01-01
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| Series: | International Journal of Advanced Nuclear Reactor Design and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S246860502030003X |
| _version_ | 1830136642892988416 |
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| author | Seon Oh Yu Min Ki Cho Kyung Lok Baek |
| author_facet | Seon Oh Yu Min Ki Cho Kyung Lok Baek |
| author_sort | Seon Oh Yu |
| collection | DOAJ |
| description | The code assessment on the design basis events has been of fundamental importance to the safety analyses of the nuclear power plants. When a system analysis code is released to the new version by improving the existing models and correcting the found errors, it is essential to make sure that the updated code can predict and simulate reasonably the important phenomena possibly observed during the transient. This work has focused on strengthening the predictability and reliability of the system analysis code by benchmarking the invaluable loss-of-coolant-accident (LOCA) data obtained from an integral effect test facility (RD-14M). In this study, the verification tests of the inlet-header break simulating the LOCA of the CANDU-6 plants were selected as a benchmark case for MARS-KS code evaluation. First, a proper analysis model to benchmark the RD-14M experiment was envisioned into the MARS-KS input model and its steady-state conditions were achieved successfully. Subsequently, through the transient analysis experimental data of void fraction, header pressure, differential pressure between headers, and sheath temperature were compared with the code results. The code input models predicted the experimental results of the transient conditions with a good agreement. Through this study, it is expected that the MARS-KS code validation for the CANDU safety analysis could be improved significantly. In addition, this study is expected to contribute to developing practical assessment problems and providing a meaningful example for direction to code improvement. |
| first_indexed | 2024-12-17T07:55:32Z |
| format | Article |
| id | doaj.art-80e5f6d2c50a4dfab0550acaf0450e96 |
| institution | Directory Open Access Journal |
| issn | 2468-6050 |
| language | English |
| last_indexed | 2024-12-17T07:55:32Z |
| publishDate | 2020-01-01 |
| publisher | KeAi Communications Co., Ltd. |
| record_format | Article |
| series | International Journal of Advanced Nuclear Reactor Design and Technology |
| spelling | doaj.art-80e5f6d2c50a4dfab0550acaf0450e962022-12-21T21:57:44ZengKeAi Communications Co., Ltd.International Journal of Advanced Nuclear Reactor Design and Technology2468-60502020-01-01219Numerical assessment of LOCA experiments of RD-14M using MARS-KS codeSeon Oh Yu0Min Ki Cho1Kyung Lok Baek2Corresponding author.; Korea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon, 34142, Republic of KoreaKorea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon, 34142, Republic of KoreaKorea Institute of Nuclear Safety, 62 Gwahak-ro, Yuseong-gu, Daejeon, 34142, Republic of KoreaThe code assessment on the design basis events has been of fundamental importance to the safety analyses of the nuclear power plants. When a system analysis code is released to the new version by improving the existing models and correcting the found errors, it is essential to make sure that the updated code can predict and simulate reasonably the important phenomena possibly observed during the transient. This work has focused on strengthening the predictability and reliability of the system analysis code by benchmarking the invaluable loss-of-coolant-accident (LOCA) data obtained from an integral effect test facility (RD-14M). In this study, the verification tests of the inlet-header break simulating the LOCA of the CANDU-6 plants were selected as a benchmark case for MARS-KS code evaluation. First, a proper analysis model to benchmark the RD-14M experiment was envisioned into the MARS-KS input model and its steady-state conditions were achieved successfully. Subsequently, through the transient analysis experimental data of void fraction, header pressure, differential pressure between headers, and sheath temperature were compared with the code results. The code input models predicted the experimental results of the transient conditions with a good agreement. Through this study, it is expected that the MARS-KS code validation for the CANDU safety analysis could be improved significantly. In addition, this study is expected to contribute to developing practical assessment problems and providing a meaningful example for direction to code improvement.http://www.sciencedirect.com/science/article/pii/S246860502030003XPHWRCANDU-6LOCAMARS-KSRD-14M |
| spellingShingle | Seon Oh Yu Min Ki Cho Kyung Lok Baek Numerical assessment of LOCA experiments of RD-14M using MARS-KS code International Journal of Advanced Nuclear Reactor Design and Technology PHWR CANDU-6 LOCA MARS-KS RD-14M |
| title | Numerical assessment of LOCA experiments of RD-14M using MARS-KS code |
| title_full | Numerical assessment of LOCA experiments of RD-14M using MARS-KS code |
| title_fullStr | Numerical assessment of LOCA experiments of RD-14M using MARS-KS code |
| title_full_unstemmed | Numerical assessment of LOCA experiments of RD-14M using MARS-KS code |
| title_short | Numerical assessment of LOCA experiments of RD-14M using MARS-KS code |
| title_sort | numerical assessment of loca experiments of rd 14m using mars ks code |
| topic | PHWR CANDU-6 LOCA MARS-KS RD-14M |
| url | http://www.sciencedirect.com/science/article/pii/S246860502030003X |
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