Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase
Micro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical–CO2–cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovat...
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Format: | Article |
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Elsevier
2021-02-01
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Series: | Nuclear Engineering and Technology |
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Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573320301935 |
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author | Eunseo So Man Cheol Kim |
author_facet | Eunseo So Man Cheol Kim |
author_sort | Eunseo So |
collection | DOAJ |
description | Micro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical–CO2–cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovative design concepts. It adopted a modular design and passive safety systems to minimize site constraints. As the MMR is in its conceptual design phase, design weaknesses and valuable safety insights could be identified during PSA. Level 1 internal event PSA was carried out involving literature survey, system characterization, identification of initiating events, transient analyses, development of event trees and fault trees, and quantification. The initiating events and scenarios significantly contributing to core damage frequency (CDF) were determined to identify design weaknesses in MMR. The most significant initiating event category contributing to CDF was the transients with the power conversion system initially available category, owing to its relatively high occurrence frequency. Further, an importance analysis revealed that the safety of MMR can be significantly improved by improving the reliability of reactor trip and passive decay heat removal system operation. The findings presented in this paper are expected to contribute toward future applications of PSA for assessing unconventional nuclear reactors in their conceptual design phases. |
first_indexed | 2024-12-17T20:17:45Z |
format | Article |
id | doaj.art-5b488541b8454ba4b40b5c9eb1c5c93a |
institution | Directory Open Access Journal |
issn | 1738-5733 |
language | English |
last_indexed | 2024-12-17T20:17:45Z |
publishDate | 2021-02-01 |
publisher | Elsevier |
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series | Nuclear Engineering and Technology |
spelling | doaj.art-5b488541b8454ba4b40b5c9eb1c5c93a2022-12-21T21:34:02ZengElsevierNuclear Engineering and Technology1738-57332021-02-01532498508Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phaseEunseo So0Man Cheol Kim1Department of Energy Systems Engineering, Chung-Ang University, 84 Heukseok-ro, Dongjak-gu, Seoul, 06974, Republic of KoreaCorresponding author.; Department of Energy Systems Engineering, Chung-Ang University, 84 Heukseok-ro, Dongjak-gu, Seoul, 06974, Republic of KoreaMicro reactors are increasingly being considered for utilization as distributed power sources. Hence, the probabilistic safety assessment (PSA) of a direct supercritical–CO2–cooled fast reactor, called micro modular reactor (MMR), was performed in this study; this reactor was developed using innovative design concepts. It adopted a modular design and passive safety systems to minimize site constraints. As the MMR is in its conceptual design phase, design weaknesses and valuable safety insights could be identified during PSA. Level 1 internal event PSA was carried out involving literature survey, system characterization, identification of initiating events, transient analyses, development of event trees and fault trees, and quantification. The initiating events and scenarios significantly contributing to core damage frequency (CDF) were determined to identify design weaknesses in MMR. The most significant initiating event category contributing to CDF was the transients with the power conversion system initially available category, owing to its relatively high occurrence frequency. Further, an importance analysis revealed that the safety of MMR can be significantly improved by improving the reliability of reactor trip and passive decay heat removal system operation. The findings presented in this paper are expected to contribute toward future applications of PSA for assessing unconventional nuclear reactors in their conceptual design phases.http://www.sciencedirect.com/science/article/pii/S1738573320301935Advanced reactorProbabilistic safety assessmentInitiating event categoryEvent tree analysisFault tree analysisPassive safety system |
spellingShingle | Eunseo So Man Cheol Kim Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase Nuclear Engineering and Technology Advanced reactor Probabilistic safety assessment Initiating event category Event tree analysis Fault tree analysis Passive safety system |
title | Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase |
title_full | Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase |
title_fullStr | Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase |
title_full_unstemmed | Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase |
title_short | Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase |
title_sort | level 1 probabilistic safety assessment of supercritical co2 cooled micro modular reactor in conceptual design phase |
topic | Advanced reactor Probabilistic safety assessment Initiating event category Event tree analysis Fault tree analysis Passive safety system |
url | http://www.sciencedirect.com/science/article/pii/S1738573320301935 |
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