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ASRAM2020-IL01
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Risk Communication for Scientists and Engineers
Mariko Nishizawa (LITERA JAPAN, Japan)
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ASRAM2020-1009
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Development of an interface tool to create Level 3 PRA analysis input data from Level 2 PRA analysis outcomes
Fumie Sebe, Hideki Horie, Mika Tahara, Kaoru Matsushita, Hiroki Suzuki (Toshiba Energy Systems & Solutions Corporation, Japan)
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ASRAM2020-1023
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Development of the Multi-Site/Unit Risk Assessment Method Based on Continuous Markov Monte Carlo Method and Bayesian Networks: (1) Modeling Method of Interactive Accident Scenarios with a Multi-Site/Unit PRA
Tomomi Hanai, Satoshi Shinzaki, Kensuke Toyoshima, Takamasa Kurokawa, Masayuki Hijiya (Nuclear Engineering, Ltd., Japan), Sunghyon Jang, Akira Yamaguchi (University of Tokyo, Japan), Takeshi Suminaga, Satoshi Takeda, Takanori Kitada (Osaka University, Japan)
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ASRAM2020-1031
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Development of the Multi-Site/Unit Risk Assessment Method Based on Continuous Markov Monte Carlo Method and Bayesian Networks: (2) Assessment of Mitigation Strategy Using Concept of FLEX
Sunghyon Jang, Akira Yamaguchi (The University of Tokyo, Japan), Tomomi Hanai, Satoshi Shinzaki, Kensuke Toyoshima, Takamasa Kurokawa, Hijiya Masayuki (Nuclear Engineering, Ltd, Japan)
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ASRAM2020-1027
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Study on Multi-unit/Multi-source PRA considering Correlation between Multiple Safety Systems using the Continuous Markov chain Monte Carlo Method
Kento Sawada, Tomohiro Endo, Akio Yamamoto (Nagoya University, Japan), Sunghyon Jang (The University of Tokyo, Japan), Daisuke Fujiwara, Chikahiro Sato (TEPCO SYSTEMS CORPORATION, Japan)
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ASRAM2020-1050
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A Framework for Dynamic PSA using System Performance-based Surrogate Method
Jong Woo Park, Seung Jun Lee (Ulsan National Institute of Science and Technology, Korea)
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ASRAM2020-1052
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Estimation of Site Operating States for Multi-unit Nuclear Power Plants using Monte-Carlo Method
Heejong Yoo, Kyungho Jin, Gyunyoung Heo (Kyunghee University, Korea)
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ASRAM2020-1075
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Identification of Multi-unit Commonalities in the Operational Events of Korean Nuclear Power Plants
Hakkyu Lim (KEPCO INTERNATIONAL NUCLEAR GRADUATE SCHOOL, Korea)
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ASRAM2020-1055
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Uncertainty analysis for inter-unit CCF and intra-unit CCF in multi-unit seismic PSA
Yunyeong Heo, Seung Jun Lee (Ulsan national institute of science and technology, Korea)
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ASRAM2020-1059
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Case Study on Sampling Techniques Using Machine Learning and Simplified Physical Model for Simulation-Based Dynamic Probabilistic Risk Assessment
Kotaro Kubo, Xiaoyu Zheng, Jun Ishikawa, Tomoyuki Sugiyama (Japan Atomic Energy Agency, Japan), Sunghyon Jang, Takashi Takata, Akira Yamaguchi (The University of Tokyo, Japan)
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ASRAM2020-1061
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Quantitative risk assessment of passive decay heat removal system
Eunseo So, Man Cheol Kim (Chung-Ang University, Korea)
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ASRAM2020-1025
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The analysis for ex-vessel debris coolability of BWR
Toshinori Matsumoto, Yuzuru Iwasawa, Kohei Ajima, Tomoyuki Sugiyama (Japan Atomic Energy Agency, Japan)
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ASRAM2020-1033
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Assessment of Accident Mitigation Strategies for ISLOCA using MELCOR
Seungwoo Kim, Yerim Park, Youngho Jin, Dong Ha Kim, Moosung Jae (Hanyang University, Korea)
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ASRAM2020-1048
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Study on the Appropriateness of Pre-flooding Strategy Considering the Risk of MCCI vs. FCI in ABWR
Yuriko Onishi, Hiromasa Chitose, Satoshi Watanabe (Hitachi-GE Nuclear Energy, Ltd., Japan)
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ASRAM2020-1005
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An Approach to Modeling FLEX/MACST Strategies into PSAs by Considering Natural Hazards
Young A Suh, Jaewhan Kim, Mee-Jeong Hwang (Korea Atomic Energy Research Institute , Korea)
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ASRAM2020-1049
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Consideration of Cybersecurity Analysis Approach of Instrumentation and Control System of Thai Research Reactor-1/Modification 1 under Probabilistic Risk Assessment
Wasin Vechgama, Chotika Dararutana, Anantachai Pechrak, Saensuk Wetchagarun (Thailand Institute of Nuclear Technology (Public Organization), Thailand), Kampanart Silva (National Energy Technology Center, Thailand)
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ASRAM2020-1064
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Study and Application of Human Reliability Analysis for Seismic Event
Guixue Zhu, Yongping Qiu, Jingjing Liu, Leilei Xu (SNERDI, China)
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ASRAM2020-1074
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Comparing selection of representatives of ground acceleration intervals in Seismic Probabilistic Safety Assessment
Byeongcheon Go, Hakkyu Lim (KEPCO INTERNATIONAL NUCLEAR GRADUATE SCHOOL, Korea)
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ASRAM2020-1010
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Integration of Transportation Simulation with a Level 3 PRA Code for Nuclear Power Plants
Kazumasa Shimada (Japan Atomic Energy Agency, Japan), Justin Pence, Tatsuya Sakurahara, Seyed Reihani, Zahra Mohaghegh (University of Illinois Urbana-Champaign, United States)
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ASRAM2020-1046
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An Effectiveness Analysis of Staged Evacuation During Severe Accidents
Sunghyun Park, Mina Cho, Seokwoo Sohn, Moosung Jae (Hanyang University, Korea)
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ASRAM2020-1072
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Review and Application of Emergency Phase Resuspension Models to Radiological Consequence Analysis
Sung-Yeop Kim (Korea Atomic Energy Research Institute, Korea), Nathan E. Bixler (Sandia National Laboratories, United States), Sukhoon Kim (FNC Technology Co., Korea)
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ASRAM2020-1040
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Reexploring Landscape of Energy Resilience Research
Pichayaluck Patumwongsakorn (Kasetsart University, Thailand), Kampanat Thapmanee, Phumanan Niyomna (National Metal and Materials Technology Center , Thailand), Naraphorn Paoprasert (Kasetsart University, Thailand), Preecha Sriprapakhan (Mahasarakham University, Thailand), Nuwong Chollacoop, Kampanart Silva (National Metal and Materials Technology Center, Thailand)
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ASRAM2020-1041
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Threat Identification for Energy Resilience Assessment of Renewable Energy Systems: A Case Study of the 700 kW Solar Power Plant in Northern Thailand
Naphat Phuengdecha (Kasetsart University, Thailand), Nattapat Leeraphan, Worajit Setthapun, Hathaithip Sintuya (Chiang Mai Rajabhat University, Thailand), Naraphorn Paoprasert (Kasetsart University, Thailand), Preecha Sriprapakhan (Mahasarakham University, Thailand), Nuwong Chollacoop, Kampanart Silva (National Metal and Materials Technology Center, Thailand)
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ASRAM2020-1069
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Risk assessment of digital I&C system based on STPA and its implication for PSA
Sung-Min Shin, Sang Hun Lee, Seung Ki Shin ( Korea Atomic Energy Research Institute, Korea), Inseok Jang (KAERKorea Atomic Energy Research Institute, Korea)
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ASRAM2020-1021
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Risk-informed evaluation of Severe Accident measures contribution to plant safety in Ohma Nuclear Power Plant
Takahiro Okuno, Naoki Yanagisawa, Tsukasa Ootani, Hiroshi Shiota (Electric Power Development Company, Japan)
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ASRAM2020-1047
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Assessment of Risk-Informed Maintenance Strategy for BWR Plants
Kotaro Yoshizaki, Bumpei Fujioka (Hitachi-GE Nuclear Energy, Ltd., Japan), Atsushi Nemoto (Hitachi Industry & Control Solutions, Ltd., Japan)
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ASRAM2020-1054
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JANSI’S ACTIVITIES OF RISK MANAGEMENT IN JAPANESE NUCLEAR INDUSTRIES
Keiko Chitose, Takeshi Tamura, Yoshikazu Uno, Naoyuki Murata, Yushi Ono, Yoichi Nishimura (Japan Nuclear Safety Institute, Japan)
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ASRAM2020-1073
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RISMC METHODOLOGY RESEARCH AND APPLICATION---SBO SPECIFIC SEQUENCE ANALYSIS AND CONDITIONAL EXCEEDANCE PROBABILITY CALCULATION
Yun Du (Shanghai Nuclear Engineering Research & Design Institute CO., LTD., China), Kuo-Shing Liang (Shanghai Jiao Tong University, China), Qinfang Zhang (Shanghai Nuclear Engineering Research & Design Institute, China)
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ASRAM2020-1012
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Study on Quantitative Evaluation Method of Interaction Multi-layer Model for Accidents in Nuclear Fuel Facilities Caused by Earthquake
Kenji Mori, Hitoshi Muta, Yasuki Ohtori (Tokyo City University, Japan)
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ASRAM2020-1076
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Study on Application of Safety Evaluation Methods for Spent Fuel Reprocessing Facilities
Jinghan Zhang, Jun Zhao (Tsinghua University, China), Dan Lv (Nuclear and Radiation Safety Center, China)
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ASRAM2020-1043
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An Empirical Comparative Study on International Cooperation in Nuclear Safety in Japan and Korea
Sungha Park (POSCO, Korea)
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ASRAM2020-KL01
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New Initiative of Risk-informed Applications in JAEA
Tsuyoshi Takada (Japan Atomic Energy Agency, Japan)
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ASRAM2020-KL02
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A Way toward RIDM: Korean Experiences and Future Plan
Joon-Eon Yang (Korea Atomic Energy Research Institute, Korea)
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ASRAM2020-KL03
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Some Practices and Considerations in Risk-informed application in China
Wei Deng (China Nuclear Power Engineering Company, China)
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ASRAM2020-1003
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Comparison of off-site support among Japan and other countries
Ryota Moriyama, Takanori Kitada, Satoshi Takeda (Osaka University, Japan), Satoshi Shinzaki, Tomomi Hanai, Takamasa Kurokawa, Masayuki Hijiya (Nuclear Engineering Ltd, Japan), Akira Yamaguchi, Jang Sunghyon (University of Tokyo, Japan)
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ASRAM2020-1008
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Sensitivity analysis on effectiveness of off-site personnel support for preventing severe accidents
Takeshi Suminaga, Takanori Kitada, Satoshi Takeda (OSAKA UNIVERSITY, Japan), Akira Yamaguchi, Shunghyon Jang (TOKYO UNIVERSITY, Japan), Masayuki Hijiya, Takamasa Kurokawa, Satoshi Shinzaki, Tomomi Hanai (NUCLEAR ENGINEERING, Ltd, Japan)
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ASRAM2020-1018
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classification of ground motion temporal characteristics with cluster analysis for regional seismic damage assesment
Kou Kawamata, Tatsuya Itoi, Chen Dongyue, Naoto Sekimura (University of Tokyo, Japan)
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ASRAM2020-1036
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Study on the Seismic-Volcano Level 1 PRA Methodology
Kota Sakama, Hitoshi Muta (Tokyo City University, Japan)
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ASRAM2020-1038
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Case Study of Seismic Risk Evaluation Considering Periodic Correlation
Yosei Tateno, Hitoshi Muta, Yasuki Ohtori (Tokyo City University, Japan)
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ASRAM2020-1056
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Analysis of Success Criteria for POS5 in Westinghouse and Korean Standard Reactors using MARS-KS
Dohun Kwon, Gyunyoung Heo, Eojin Jeon (Kyung Hee University, Korea)
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ASRAM2020-1070
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Application of PSA Technology in Spent Fuel Reprocessing Plants
Guanyv Liu (North China Electric Power University, China)
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ASRAM2020-1037
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Availability Analysis of RPS with Multiple Platforms(PLC, FPGA)
Jiye Jeong, Gyunyoung Heo (Kyung Hee University, Korea), Ibrahim Ahmed (Politecnico di Milano, Italy, Nigeria)
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ASRAM2020-1044
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Multi-unit risk informed decision-making in AAC DG sharing operation
Mina Cho, Yongjin Kim, Sunghyun Park, Moosung Jae (Hanyang university, Korea)
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ASRAM2020-1057
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Development of the COFUN Code for Level 2 PSA Uncertainty Analysis
Dohyun Lim, Byeongmun Ahn, Youngho Jin, Moosung Jae (Hanyang University, Korea)
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ASRAM2020-1063
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THE EFFECT OF CLIMATE CONDITION EVALUATION UNCERTAINTY ON THE PCCS in AP1000
Yu Yu, Wanxin Feng, Zhangpeng Guo, Fenglei Niu (North China Electric Power University, China), Yan Dong (2Beijing Meteorological Service Center, China)
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ASRAM2020-1004
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Internal event Level-1 PRA for sodium-cooled fast reactor considering safety measures of Defense-in-depth level 1 to 3
Hiroyuki Nishino, Kenichi Kurisaka (Japan Atomic Energy Agency, Japan), Kenichi Naruto (NESI Inc., Japan), Yoji Gondai, Masaya Yamamoto, Hidemasa Yamano (Japan Atomic Energy Agency, Japan)
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ASRAM2020-1013
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Investigation on the PSA Application in the Designing Process of Nuclear Power Plant
Dingqing Guo (Shanghai Jiao Tong University/China Nuclear Power Engineering Co., China), Xuewu Cao (Shanghai Jiao Tong University, China), Zhixin Xu (China Nuclear Power Engineering Co., China), Lili Tong (Shanghai Jiao Tong University, China)
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ASRAM2020-1016
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Trial estimation of alpha factors for 16 safety relief valves (SRVs) by using a minimally informative Dirichlet prior (MIDP) as a prior distribution
Tomohiko Ikegawa (Hitachi, Ltd., Japan), Ryusuke Kimura (Hitachi-GE Nuclear Energy, Japan)
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ASRAM2020-1065
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Research on Bounding Assessment Method for Motor-Driven Fire Pump Outage in Nuclear Power Plant
Zhen Yan, Yucheng Zhuo (SNERDI, China), Jun Xiao (National Nuclear Safety Adminstration, China), Yifeng Shi (CNNP, China), Zhaohua Li (SNERDI, China)
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ASRAM2020-1028
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Ideal way of method and data issues in Human Reliability Analysis (HRA) (1) Extraction of HRA method issues by comparison analysis
Yoshihiro Ide (AdvanceSoft Corporation, Japan), Hiroshi Ujita (AdvanceSoft Corporation, Japan Nuclear Safety Institute, Japan)
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ASRAM2020-1030
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Ideal way of method and data issues in Human Reliability Analysis (HRA) (2) Extraction of method and data issues from research survey
Hiroshi Ujita (AdvanceSoft Corporation, Japan Nuclear Safety Institute, Japan), Yoshihiro Ide (AdvanceSoft Corporation, Japan)
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ASRAM2020-1066
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A Time-based Analysis of Human Reliability for a Severe Accident Management Strategy
Young A Suh, Jaewhan Kim, Soo Yong Park (Korea Atomic Energy Research Institute, Korea)
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ASRAM2020-1071
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A Framework of Level 2 HRA for Analyzing SAMG-based Actions
Jaewhan Kim, Young A Suh (Korea Atomic Energy Research Institute, Korea)
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