| 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 | 45 | 2016 |
| 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 | 21 | 2019 |
| 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 | 15 | 2020 |
| 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 | 14 | 2019 |
| 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 | 10 | 2020 |
| 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 | 10 | 2019 |
| 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 | 9 | 2021 |
| 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 | 9 | 2020 |
| 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 | 7 | 2022 |
| 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 | 7 | 2022 |
| Treating Common-Cause Failures in Multi-unit PRAs S Zhang, J Tong, J Wu International Topical Meeting on Probabilistic Safety Assessment and …, 2017 | 7 | 2017 |
| 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 | 6 | 2020 |
| 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 | 4 | 2023 |
| 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 | 3 | 2021 |
| Incorporating FLEX Strategies in Multi-Unit Probabilistic Risk Assessment S Zhang, Z Ma International Conference on Nuclear Engineering 83778, V002T10A013, 2020 | 3 | 2020 |
| 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 | 2 | 2023 |
| 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 | 2 | 2020 |
| 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 | 1 | 2023 |
| An Integrated Framework for Risk Assessment of Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology Refinement and Exploration H Bao, TH Shorthill, E Chen, J Park, J Kim, GS Turkmen, H Ban, N Dinh, ... Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 1 | 2023 |
