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PROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025

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论文数49
被引数
期刊论文 49
发表时间
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Research and Application of Risk Analysis Methods for Extending the Test Intervals of Containment Penetration Leakage Rate Tests in Nuclear Power Plants核电厂 containment penetration 泄漏率试验测试间隔延长的风险分析方法研究与应用
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteLiang Xiaoyu; Wang Handing; Gu Songying; Feng Bingchen
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Theoretical Investigation of F-C Curves for Non-light Water Reactors and Comparison with Probabilistic Safety Objectives of HTGRs非轻水反应堆F-C曲线的理论研究及其与高温气冷堆概率安全目标的比较
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteHe, Jie; Tan, Guofeng; Shi, Jin; Huang, Ning; Zhou, Zhende; Guo, Ruonan; Zhou, Qin; Xu, Zuxuan; Hong, Yujia; Tang, Xingwang; Dai, Yangcong; Li, Chao; Chen, Junjie; Xiao, Sanping
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Quantitative Method for Seismic PSA Optimization Based on Binary Decision Diagrams基于二元决策图的地震PSA定量优化方法
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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deleteSong Jinyang; Shi Qi; Qu Bin; Yan Jiayu; Zhang Zhuo
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Validation of SPRUCE Code with Aerosol Deposition Experiment in a Containment with Heat Exchanger Tubes在带换热器管的 containment 中进行气溶胶沉积实验验证 SPRUCE 代码
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteChen Yongzheng; Ouyang Yong; Ou Pingwen; Liao Feiye; E Xinnuo; Chen Peng; Guo Chao; Gu Haifeng
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PSA Application for High Energy Line Breaks in Nuclear Power PlantsPSA在核电站高能管道断裂中的应用
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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PREAI
deleteWang, Zhiwen; Wu, Yulong; Sang, Huina; Tang, Xiaoming; Yang, Chunju; Wang, Jinkai
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Methods for Calculating the Safety Significance of Nuclear Power Plant Functions Based on Risk-Informed Approach基于风险指引方法计算核电厂功能安全重要性的方法
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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deleteWang, Xiaofan; Gao, Wei; Peng, Xiaochun; Yan, Zhen; Wang, Wensheng
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Research on the Application of Risk-Informed Safety Classification in the Field of Repair/Replacement风险知情安全分类在维修/更换领域的应用研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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PREAI
deleteLi Long; Yang Jianfeng; Zhang Zefeng; Yang Zhi; Sun Jiajia; Geng Kui
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Research on the Method of Internal Flooding Safety Assessment for Small Modular Reactor小型模块化反应堆内部 flooding 安全评估方法研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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PREAI
deleteChen, Liping; Liang, Bo; Wu, Fuyu
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CFD Code Validation on NACIE-UP Rod Bundle: Review on Numerical Methods and ResultsNACIE-UP棒束CFD代码验证：数值方法与结果的综述
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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deleteLi, Haoyang; Zhang, Dalin; Tian, Wenxi; Qiu, Suizheng
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Reliability Data Analysis and Research of Emergency Diesel Generator Sets in Nuclear Power Plants核电厂应急柴油发电机组可靠性数据分析与研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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PREAI
deleteChen, Li-hui; Zhang, Yong; Wang, Fen; Chen, Shi-jun; Tang, Fei-fei
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Development and Validation of a Turbulent Combustion Model for CO/H2/Air MixturesCO/H2/空气混合物的湍流燃烧模型开发与验证
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteLiu, Siqi; Li, Yabing; Ouyang, Yong; Zhao, Xinhai
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Research on the Key Parameters of the Natural Circulation Cooling Process in Lead-Bismuth Fast Reactor Based on Analytic Hierarchy Process基于层次分析法对铅铋快堆自然循环冷却过程关键参数的研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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PREAI
deleteWang, Qilong; Wang, Yichun; Yu, Yu
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Reliability Analysis of the Safety Function of the Secondary Side Passive Residual Heat Removal System in HPR1000HPR1000次级侧被动余热排出系统安全功能可靠性分析
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteXiong, Zhenpeng; Chen, Shi; Yang, Benlin; Zhao, Xinyue; Hu, Lingsheng; Zhao, Guanghui; Zheng, Junming
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Validation of a Transient Analysis Program for Heat Pipe Cooled Reactors Based on KRUSTY Experiments基于KRUSTY实验的热管冷却反应堆瞬态分析程序验证
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteShao, Kunpeng; Guo, Ziang; Liu, Changhe; Liu, Ziyin; Liu, Limin; Gu, Hanyang
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Study on Relay Desensitization of Main Feedwater Regulating Valves in a Second-Generation Nuclear Power Plant研究二代核电站主给水调节阀的继电器去敏化
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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deleteHu Yuehua; Liu Jingjing; Chen Jiaqing; Zhao Ming; Liu Yong
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Integrating Large Language Models with Retrieval-Augmented Generation for Decision Support in IDHEAS-ECA Applications将大型语言模型与检索增强生成相结合，以支持IDHEAS-ECA应用中的决策
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteXiao, Xingyu; Chen, Peng; Liang, Jingang; Tong, Jiejuan; Wang, Haitao
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Research on Distributed Coupled Computational Methods Based on the Vitars Platform基于Vitars平台的分布式耦合计算方法研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteXiao, Qianxi; Wan, Dezhi; Chen, Ronghua; Zhang, Liqun; Ni, Si; Tian, Wenxi; Qiu, Suizheng
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Research of the Risk of Interfacing-System Loss-Of-Coolant Accident for HPR1000HPR1000接口系统失水事故风险研究
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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deleteJian, Yang; Ran, Feng Chu
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Development of Validation Matrix of Fuel Assembly Thermal-Hydraulics Sub-channel Analysis Code for Sodium-Cooled Fast Reactors钠冷快堆燃料组件热工水力子通道分析代码的验证矩阵开发
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteKikuchi, Norihiro; Yoshikawa, Ryuji; Tanaka, Masaaki
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Analysis of Severe Accident Risk of Gen II Nuclear Power Plants Based on Internal Event Level 2 Probabilistic Safety Assessment基于内部事件二级概率安全评估的二代核电站严重事故风险分析
deletePROCEEDINGS OF THE 32ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING-VOL 15; ICONE 2025
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delete2026-01-01
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deleteGuo, Shujie; Yu, Yun; Liang, Jingyi; Li, Wenjing; Wei, Wei; Yu, Xinli
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