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Sai Zhang
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An integrated modeling approach for event sequence development in multi-unit probabilistic risk assessment
S Zhang, J Tong, J Zhao
Reliability Engineering & System Safety 155, 147-159, 2016
472016
Multi-objective optimization of maintenance program in multi-unit nuclear power plant sites
S Zhang, M Du, J Tong, YF Li
Reliability Engineering and System Safety 188, 532-548, 2019
192019
Integrating renewal process modeling with Probabilistic Physics-of-Failure: Application to Loss of Coolant Accident (LOCA) frequency estimations in nuclear power plants
T Sakurahara, N O'Shea, WC Cheng, S Zhang, S Reihani, E Kee, ...
Reliability Engineering & System Safety 190, 106479, 2019
172019
Integrated Risk-Informed Design (I-RID) Methodological Framework and Computational Application for FLEX Equipment Storage Buildings of Nuclear Power Plants
G Schumock, S Zhang, P Farshadmanesh, JG Owens, N Kasza, J Stearns, ...
Progress in Nuclear Energy, 2020
162020
Review and categorization of existing studies on the estimation of probabilistic failure metrics for Reactor Coolant Pressure Boundary piping and steam generator tubes in …
WC Cheng, T Sakurahara, S Zhang, P Farshadmanesh, S Reihani, E Kee, ...
Progress in Nuclear Energy 118, 103105, 2020
112020
Exploring Advanced Computational Tools and Techniques with Artificial Intelligence and Machine Learning in Operating Nuclear Plants
Z Ma, H Bao, S Zhang, M Xian, A Mack
https://doi.org/10.2172/1847070, 2022
102022
Multicriterion Benefit Evaluation Methodology for Safety Enhancements in Nuclear Power Plants and Application for FLEX Strategies
S Zhang, Z Ma, H Zhang, CL Smith
Nuclear Engineering and Design 376, 2021
102021
Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model
Z Ma, C Davis, C Parisi, R Dailey, J Wang, S Zhang, H Zhang, M Corradini
https://doi.org/10.2172/1777262, 2019
102019
Causality Extraction from Nuclear Licensee Event Reports Using a Hybrid Framework
S Rahman, S Zhang, M Xian, S Sun, F Xu, Z Ma
https://arxiv.org/abs/2404.05656, 2024
92024
An Integrated Framework for Risk Assessment of High Safety Significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and …
H Bao, T Shorthill, E Chen, J Park, S Zhang, AV Jayakumar, C Elks, ...
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2022
92022
Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under DesignBasis and Beyond-Design-Basis Accidents
Z Ma, S Zhang, H Zhang, J Park, J Yu, C Blakely, TA Ulrich, RL Boring
https://doi.org/10.2172/1777266, 2020
92020
Treating Common-Cause Failures in Multi-unit PRAs
S Zhang, J Tong, J Wu
International Topical Meeting on Probabilistic Safety Assessment and …, 2017
92017
Common-Cause Component Group Modeling Issues in Probabilistic Risk Assess
Z Ma, RF Buell, JK Knudsen, S Zhang
Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020
62020
Risk Analysis of Various Design Architectures for High Safety-significant Safety-related Digital Instrumentation and Control Systems of Nuclear Power Plants during Accident …
H Bao, S Zhang, RW Youngblood III, T Shothill, P Pandit, E Chen, J Park, ...
Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023
52023
Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment
S Zhang, Z Ma
International Conference on Nuclear Engineering 83778, V002T10A013, 2020
42020
Modeling FLEX Human Actions using the EMRALD Dynamic Risk Assessment Tool. 2021 International Topical Meeting on Probabilistic Safety Assessment and Analysis
J Park, TA Ulrich, RL Boring, S Zhang, Z Ma, H Zhang
2021 International Topical Meeting on Probabilistic Safety Assessment and …, 2021
3*2021
Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology
S Zhang, H Zhang, P Park, T Liu, T Ulrich, L Boring, Z Ma, H Jiang
https://doi.org/10.2172/1885798, 2021
32021
Research Activities associated with the Treatment of Potential Common-Cause Failures in Event and Condition Assessment
C Hunter, C Ng, MR Fard, Z Ma, S Zhang
Nuclear Technology 209 (11), 1680-1687, 2023
22023
Common-Cause Component Group Modeling Issues in Probabilistic Risk Assessment
Z Ma, R Buell, J Knudsen, S Zhang
2020 ANS Virtual Winter Meeting 123 (1), D-G, 2020
22020
Research to develop flood barrier testing strategies for nuclear power plants
Z Ma, S Zhang, C Pope, C Smith
Nuclear Technology 209 (11), 1688-1696, 2023
12023
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