Research output per year
Research output per year
Personal profile
Biography
Dr. Sai Zhang works as a probabilistic risk and reliability analyst at Idaho National Laboratory, USA. Her research interests include probabilistic risk assessment (PRA), risk-informed analyses and applications, risk-cost optimization, and multicriterion benefit evaluation for nuclear power plants. She has been a key investigator on a variety of U.S. Nuclear Regulatory Commission- and Department of Energy-sponsored projects including computational support for risk applications, Standardized Plant Analysis Risk (SPAR) modeling, risk-informed analyses for enhanced resilient plant systems, flood barrier testing strategy development, and exploration of artificial intelligence/machine learning in nuclear operating experience. She holds a Ph.D. degree in nuclear engineering from Tsinghua University, China. She is a member of the American Nuclear Society (ANS). She serves in the multi-Unit PRA working group and the non-light water reactor PRA working group under the ANS/ASME Joint Committee on Nuclear Risk Management (JCNRM)..
Research Interests
Probabilistic risk assessment (PRA)
Nuclear safety
Risk-informed analyses and applications
Risk-cost optimization
Multicriterion benefit evaluation
Education/Academic qualification
PhD, Nuclear Engineering, Tsinghua University
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Collaborations and top research areas from the last five years
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Causality Extraction from Nuclear Licensee Event Reports Using a Hybrid Framework
Rahoman Sohag, S., Zhang, S., Xian, M., Sun, S., Xu, F. & Ma, Z., Jun 2024, In: Transactions of the American Nuclear Society. 130, 1, p. 840-843Research output: Contribution to journal › Conference article › peer-review
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Incorporating A Risk-Informed, Performance-Based Concept into Nuclear Fuel and Materials Development for Advanced Reactors
Zhang, S., Ma, Z. & Xu, P., Feb 27 2024.Research output: Contribution to conference › Paper › peer-review
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Incorporating a Risk-informed, Performance-based Process into Nuclear Fuel and Material Development for Advanced Reactors
Zhang, S., Ma, Z. & Xu, P., 2024, In: Transactions of the American Nuclear Society. 130, 1, p. 517-520 4 p.Research output: Contribution to journal › Conference article › peer-review
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An Approach to Modeling Postulated Software Common Cause Failures of Diverse Digital Instrumentation and Control Systems
Shorthill, T., Bao, H., Chen, E., Zhang, S. & Ban, H., 2023, Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023. American Nuclear Society, p. 1100-1109 10 p. (Proceedings of 13th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies, NPIC and HMIT 2023).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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An Integrated Framework for Risk Assessment of Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology Refinement and Exploration
Bao, H., Shorthill, T. H., Chen, E., Park, J., Kim, J., Turkmen, G. S., Ban, H., Dinh, N., Aldemir, T., Lawrence, S. & Zhang, S., Sep 15 2023Research output: Book/Report › Technical Report