Huifang Zhang , Yuntao Zheng , Yanyu Sun , Kui Ge , Shihao Wu , Yongkang Li , Yapei Zhang , Wenxi Tian , Suizheng Qiu , Guanghui Su
{"title":"ATHROC中用于被动密封空气冷却系统仿真的PAS模块的开发","authors":"Huifang Zhang , Yuntao Zheng , Yanyu Sun , Kui Ge , Shihao Wu , Yongkang Li , Yapei Zhang , Wenxi Tian , Suizheng Qiu , Guanghui Su","doi":"10.1016/j.anucene.2025.111303","DOIUrl":null,"url":null,"abstract":"<div><div>In advanced pressurized water reactors (PWR) employing the passive containment air cooling system (PAS), heat can be removed from the containment to the atmosphere. This paper established a comprehensive mathematical and physical model to simulate PAS and developed a modular PAS module based on the ATHROC to analyze its thermal–hydraulic characteristics. The accuracy of the code was validated by comparing the calculated temperatures and pressures with data obtained from GOTHIC. The results showed that differences were less than 5%, confirming the reliability of the PAS module. Then the thermo-hydraulic analysis of AP1000 containment system with PAS during a loss-of-coolant accident (LOCA) was performed using ATHROC. The findings indicated that when LOCA ocurs, the internal temperature and pressure of the containment can be maintained below the design limits. This study confirms that the PAS module possesses the capability of the thermal–hydraulic analysis of the passive containment air cooling system.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"216 ","pages":"Article 111303"},"PeriodicalIF":2.3000,"publicationDate":"2025-06-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Development of a PAS module in the ATHROC for simulation of passive containment air cooling system\",\"authors\":\"Huifang Zhang , Yuntao Zheng , Yanyu Sun , Kui Ge , Shihao Wu , Yongkang Li , Yapei Zhang , Wenxi Tian , Suizheng Qiu , Guanghui Su\",\"doi\":\"10.1016/j.anucene.2025.111303\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In advanced pressurized water reactors (PWR) employing the passive containment air cooling system (PAS), heat can be removed from the containment to the atmosphere. This paper established a comprehensive mathematical and physical model to simulate PAS and developed a modular PAS module based on the ATHROC to analyze its thermal–hydraulic characteristics. The accuracy of the code was validated by comparing the calculated temperatures and pressures with data obtained from GOTHIC. The results showed that differences were less than 5%, confirming the reliability of the PAS module. Then the thermo-hydraulic analysis of AP1000 containment system with PAS during a loss-of-coolant accident (LOCA) was performed using ATHROC. The findings indicated that when LOCA ocurs, the internal temperature and pressure of the containment can be maintained below the design limits. This study confirms that the PAS module possesses the capability of the thermal–hydraulic analysis of the passive containment air cooling system.</div></div>\",\"PeriodicalId\":8006,\"journal\":{\"name\":\"Annals of Nuclear Energy\",\"volume\":\"216 \",\"pages\":\"Article 111303\"},\"PeriodicalIF\":2.3000,\"publicationDate\":\"2025-06-15\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Annals of Nuclear Energy\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0306454925001203\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"2025/2/25 0:00:00\",\"PubModel\":\"Epub\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925001203","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"2025/2/25 0:00:00","PubModel":"Epub","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Development of a PAS module in the ATHROC for simulation of passive containment air cooling system
In advanced pressurized water reactors (PWR) employing the passive containment air cooling system (PAS), heat can be removed from the containment to the atmosphere. This paper established a comprehensive mathematical and physical model to simulate PAS and developed a modular PAS module based on the ATHROC to analyze its thermal–hydraulic characteristics. The accuracy of the code was validated by comparing the calculated temperatures and pressures with data obtained from GOTHIC. The results showed that differences were less than 5%, confirming the reliability of the PAS module. Then the thermo-hydraulic analysis of AP1000 containment system with PAS during a loss-of-coolant accident (LOCA) was performed using ATHROC. The findings indicated that when LOCA ocurs, the internal temperature and pressure of the containment can be maintained below the design limits. This study confirms that the PAS module possesses the capability of the thermal–hydraulic analysis of the passive containment air cooling system.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.