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Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion
The steel liner plays a key role in ensuring the leak-tightness of nuclear containment structures (NCSs). Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosi...
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Published in: | Applied sciences 2024-03, Vol.14 (6), p.2407 |
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description | The steel liner plays a key role in ensuring the leak-tightness of nuclear containment structures (NCSs). Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosion effects of the liner is essential to guaranteeing the safe operation of nuclear power plants. This paper presents a probabilistic safety analysis of the NCS under liner corrosion conditions. Firstly, the corrosion mechanism of the liner is elucidated, and a refined simulation method is developed to investigate the localized corrosion effects of the liner. Utilizing a probabilistic finite element method, the fragility of the NCS under loss-of-coolant accident (LOCA) conditions is evaluated. Finally, the leakage risk of the NCS at different degrees of liner corrosion is discussed. The results indicate that liner corrosion has a significant impact on the median pressure capacity and high-confidence–low-probability pressure capacity of the NCS. With the aggravation of liner corrosion, the safety margin of the NCS decreases, and the total probability of failure increases. Within the scope of this paper, the NCS can fulfill the probabilistic safety requirements. |
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Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosion effects of the liner is essential to guaranteeing the safe operation of nuclear power plants. This paper presents a probabilistic safety analysis of the NCS under liner corrosion conditions. Firstly, the corrosion mechanism of the liner is elucidated, and a refined simulation method is developed to investigate the localized corrosion effects of the liner. Utilizing a probabilistic finite element method, the fragility of the NCS under loss-of-coolant accident (LOCA) conditions is evaluated. Finally, the leakage risk of the NCS at different degrees of liner corrosion is discussed. The results indicate that liner corrosion has a significant impact on the median pressure capacity and high-confidence–low-probability pressure capacity of the NCS. With the aggravation of liner corrosion, the safety margin of the NCS decreases, and the total probability of failure increases. Within the scope of this paper, the NCS can fulfill the probabilistic safety requirements.</description><identifier>ISSN: 2076-3417</identifier><identifier>EISSN: 2076-3417</identifier><identifier>DOI: 10.3390/app14062407</identifier><language>eng</language><publisher>Basel: MDPI AG</publisher><subject>Aging ; Climate change ; Concrete ; Corrosion ; fragility ; Investigations ; leakage risk ; liner corrosion ; LOCA ; Nuclear accidents ; nuclear containment structures ; Nuclear energy ; Nuclear engineering ; Nuclear power plants ; pressure capacity ; Prestressed concrete ; Risk assessment ; Simulation ; Simulation methods ; Steel ; Temperature effects</subject><ispartof>Applied sciences, 2024-03, Vol.14 (6), p.2407</ispartof><rights>COPYRIGHT 2024 MDPI AG</rights><rights>2024 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/). Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c361t-3288d124b56a4f193f8b14d99f0b8057cb09aec19285e3bb5367b967a2ec8f573</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.proquest.com/docview/2987693941/fulltextPDF?pq-origsite=primo$$EPDF$$P50$$Gproquest$$Hfree_for_read</linktopdf><linktohtml>$$Uhttps://www.proquest.com/docview/2987693941?pq-origsite=primo$$EHTML$$P50$$Gproquest$$Hfree_for_read</linktohtml><link.rule.ids>314,777,781,25734,27905,27906,36993,44571,74875</link.rule.ids></links><search><creatorcontrib>Li, Xinbo</creatorcontrib><creatorcontrib>Gong, Jinxin</creatorcontrib><title>Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion</title><title>Applied sciences</title><description>The steel liner plays a key role in ensuring the leak-tightness of nuclear containment structures (NCSs). Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosion effects of the liner is essential to guaranteeing the safe operation of nuclear power plants. This paper presents a probabilistic safety analysis of the NCS under liner corrosion conditions. Firstly, the corrosion mechanism of the liner is elucidated, and a refined simulation method is developed to investigate the localized corrosion effects of the liner. Utilizing a probabilistic finite element method, the fragility of the NCS under loss-of-coolant accident (LOCA) conditions is evaluated. Finally, the leakage risk of the NCS at different degrees of liner corrosion is discussed. The results indicate that liner corrosion has a significant impact on the median pressure capacity and high-confidence–low-probability pressure capacity of the NCS. With the aggravation of liner corrosion, the safety margin of the NCS decreases, and the total probability of failure increases. Within the scope of this paper, the NCS can fulfill the probabilistic safety requirements.</description><subject>Aging</subject><subject>Climate change</subject><subject>Concrete</subject><subject>Corrosion</subject><subject>fragility</subject><subject>Investigations</subject><subject>leakage risk</subject><subject>liner corrosion</subject><subject>LOCA</subject><subject>Nuclear accidents</subject><subject>nuclear containment structures</subject><subject>Nuclear energy</subject><subject>Nuclear engineering</subject><subject>Nuclear power plants</subject><subject>pressure capacity</subject><subject>Prestressed concrete</subject><subject>Risk assessment</subject><subject>Simulation</subject><subject>Simulation methods</subject><subject>Steel</subject><subject>Temperature effects</subject><issn>2076-3417</issn><issn>2076-3417</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><sourceid>PIMPY</sourceid><sourceid>DOA</sourceid><recordid>eNpNUctq3DAUNaWFhjSr_oCgy-JUL1vSchiaJmBa6GNtrl5GkxlpKsmL_EM_unKmlEgLXc495-g-uu49wbeMKfwJzmfC8Ug5Fq-6K4rF2DNOxOsX8dvuppQDbkcRJgm-6v7cZVjCMdQnBNGiycEjLA59D-UR7UpxpZxcrCh59HU1RwcZ7VOsEOIz_KPm1dQ1O7RG6zKaUil98v0-pSO0_M6YYDdiE9lQQ4plC0sDc4gLmkJ0m2POqbTku-6Nh2NxN__e6-7X3eef-_t--vblYb-besNGUntGpbSEcj2MwD1RzEtNuFXKYy3xIIzGCpwhisrBMa0HNgqtRgHUGekHwa67h4uvTXCYzzmcID_NCcL8DKS8zJBraP3OWInRMbz9aDkopkEbraX1ShrFR2heHy5e55x-r67U-ZDWHFv5M1VSjIopThrr9sJaoJmG6FPNYNq17hRMis6Hhu-ElJRTRXkTfLwITBtNyc7_L5PgeVv3_GLd7C_TuJ5n</recordid><startdate>20240301</startdate><enddate>20240301</enddate><creator>Li, Xinbo</creator><creator>Gong, Jinxin</creator><general>MDPI AG</general><scope>AAYXX</scope><scope>CITATION</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>CCPQU</scope><scope>DWQXO</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>DOA</scope></search><sort><creationdate>20240301</creationdate><title>Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion</title><author>Li, Xinbo ; Gong, Jinxin</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c361t-3288d124b56a4f193f8b14d99f0b8057cb09aec19285e3bb5367b967a2ec8f573</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><topic>Aging</topic><topic>Climate change</topic><topic>Concrete</topic><topic>Corrosion</topic><topic>fragility</topic><topic>Investigations</topic><topic>leakage risk</topic><topic>liner corrosion</topic><topic>LOCA</topic><topic>Nuclear accidents</topic><topic>nuclear containment structures</topic><topic>Nuclear energy</topic><topic>Nuclear engineering</topic><topic>Nuclear power plants</topic><topic>pressure capacity</topic><topic>Prestressed concrete</topic><topic>Risk assessment</topic><topic>Simulation</topic><topic>Simulation methods</topic><topic>Steel</topic><topic>Temperature effects</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Li, Xinbo</creatorcontrib><creatorcontrib>Gong, Jinxin</creatorcontrib><collection>CrossRef</collection><collection>ProQuest Central (Alumni)</collection><collection>ProQuest Central</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>ProQuest One Community College</collection><collection>ProQuest Central Korea</collection><collection>Publicly Available Content Database</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>DOAJ Directory of Open Access Journals</collection><jtitle>Applied sciences</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Li, Xinbo</au><au>Gong, Jinxin</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion</atitle><jtitle>Applied sciences</jtitle><date>2024-03-01</date><risdate>2024</risdate><volume>14</volume><issue>6</issue><spage>2407</spage><pages>2407-</pages><issn>2076-3417</issn><eissn>2076-3417</eissn><abstract>The steel liner plays a key role in ensuring the leak-tightness of nuclear containment structures (NCSs). Once the liner is subjected to corrosion, its corrosion effects can severely impact the leak-tight function of the NCS, especially in severe accident scenarios. Therefore, evaluating the corrosion effects of the liner is essential to guaranteeing the safe operation of nuclear power plants. This paper presents a probabilistic safety analysis of the NCS under liner corrosion conditions. Firstly, the corrosion mechanism of the liner is elucidated, and a refined simulation method is developed to investigate the localized corrosion effects of the liner. Utilizing a probabilistic finite element method, the fragility of the NCS under loss-of-coolant accident (LOCA) conditions is evaluated. Finally, the leakage risk of the NCS at different degrees of liner corrosion is discussed. The results indicate that liner corrosion has a significant impact on the median pressure capacity and high-confidence–low-probability pressure capacity of the NCS. With the aggravation of liner corrosion, the safety margin of the NCS decreases, and the total probability of failure increases. Within the scope of this paper, the NCS can fulfill the probabilistic safety requirements.</abstract><cop>Basel</cop><pub>MDPI AG</pub><doi>10.3390/app14062407</doi><oa>free_for_read</oa></addata></record> |
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subjects | Aging Climate change Concrete Corrosion fragility Investigations leakage risk liner corrosion LOCA Nuclear accidents nuclear containment structures Nuclear energy Nuclear engineering Nuclear power plants pressure capacity Prestressed concrete Risk assessment Simulation Simulation methods Steel Temperature effects |
title | Fragility and Leakage Risk Assessment of Nuclear Containment Structure under Loss-of-Coolant Accident Conditions Considering Liner Corrosion |
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