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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Main Authors: Eunseo So, Man Cheol Kim
Format: Article
Language:English
Published: Elsevier 2021-02-01
Series:Nuclear Engineering and Technology
Subjects:
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.
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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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