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浏览/检索结果: 共8条，第1-8条 帮助 已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 An improved probabilistic method for screening safety-related human actions in nuclear power plants 期刊论文 Nuclear Engineering and Design, 2018, 卷号: 340, 页码: 415-420 作者:  Zhang, Li;  Wang, Chunbo;  Zio, Enrico;  Zou, Yanhua*;  Jiang, Jianjun 收藏  |  浏览/下载：11/0  |  提交时间：2019/12/27 ASG  Auxiliary feedwater system  CDF  Core damage frequency  EPRI  Electric Power Research Institute  FV  Fussell-Vesely  HEP  Human error probability  HFE  Human factors engineering  HRA  Human reliability analysis  HRAW  Human action risk achievement worth  IAEA  International Atomic Energy Agency  LERF  Large early release frequency  NEI  Nuclear Energy Institute  NNSA  National Nuclear Safety Administration of China  NPP  Nuclear power plant  NRC  Nuclear Regulatory Commission  ONR  Office for Nuclear Regulation  PSA  Probabilistic safety assessment  RAW  Risk achievement worth  RHR  Residual heat removal system  RRW  Risk reduction worth  SDP  Significance determination process  SGTR  Steam generator tube rupture  Nuclear power plant (NPP)  Human actions  Probabilistic screening method  Human action risk achievement worth (HRAW)  Human factors engineering (HFE)   Experimental study on thermal-hydraulic behaviour of LBE and water interface 期刊论文 PROGRESS IN NUCLEAR ENERGY, 2017, 卷号: 99, 期号: 无, 页码: 1-10 作者:  Huang, Wangli;  Zhou, Danna;  Sa, Rongyuan;  Jiang, Hualei 收藏  |  浏览/下载：33/0  |  提交时间：2018/06/04 Steam Generator Tube Rupture  Molten Lbe  Fragmentation  Steam Explosion  Interfacial Instability   Experimental study on fragmentation behaviors of molten LBE and water contact interface 期刊论文 NUCLEAR SCIENCE AND TECHNIQUES, 2015, 卷号: 26, 期号: 6, 页码: 1-5 作者:  Huang Wang-Li;  Sa Rong-Yuan;  Zhou Dan-Na;  Jiang Hua-Lei;  Huang Qun-Ying 收藏  |  浏览/下载：14/0  |  提交时间：2018/01/25 Steam Generator Tube Rupture  Molten Lbe  Fragmentation  Steam Explosion  Interfacial Instability   An evaluation of designed passive Core Makeup Tank (CMT) for China pressurized reactor (CPR1000) 期刊论文 ANNALS OF NUCLEAR ENERGY, 2013, 卷号: 56, 期号: [db:dc_citation_issue], 页码: 81-86 作者:  Wang, Mingjun;  Tian, Wenxi;  Qiu, Suizheng;  Su, Guanghui;  Zhang, Yapei 收藏  |  浏览/下载：2/0  |  提交时间：2019/12/10 CMT design  CPR1000  Steam Generator Tube Rupture (SGTR)  Transient analysis   压水堆MSLB叠加SGTR事故分析 期刊论文 2010, 2010 王煦嘉; 臧希年; WANG Xujia; ZANG Xinian 收藏  |  浏览/下载：4/0 复杂人机系统班组人误模型与量化分析 期刊论文 2010, 2010 廖可兵; 刘爱群; 童节娟; 肖军; LIAO Ke-bing; LIU Ai-qun; TONG Jie-juan; XIAO Jun 收藏  |  浏览/下载：3/0 Feasibility analysis of method to avoid tube rupture in HTR-10 steam generator 期刊论文 2010, 2010 Jianling Dong; Jiyang Fu; Suyuan Yu; Yang Meng 收藏  |  浏览/下载：5/0 Accident analysis of pressurized water reactor's MSLB with SGTR 期刊论文 2010, 2010 Wang Xujia; Zang Xinian 收藏  |  浏览/下载：3/0