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Yixing Sung

Observed names: Sung, Yixing, Y. Sung, Y. X. Sung
ORCID: 0000-0003-4411-3827
Observed ORCID: 0000-0003-4411-3827
OpenAlex ID: A5086598425
Subcooled Boiling Data From Rod Bundles
2004 · Zeses E. Karoutas, Yixing Sung, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 27
Best estimate plus uncertainty analysis of departure from nucleate boiling limiting case with CASL core simulator VERA-CS in response to PWR main steam line break event
2016 · C.S. Brown, H. Zhang, et al. · Nuclear Engineering and Design · 24
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Ctf: A Modernized, Production-Level, Thermal Hydraulic Solver for the Solution of Industry-Relevant Challenge Problems in Pressurized Water Reactors
2022 · Robert Salko, Aaron Wysocki, et al. · SSRN Electronic Journal · 23
Time in DNB experimental study on Cr coated zircaloy cladding
2024 · Tiago A. Moreira, Keegan D. Murray, et al. · Applied Thermal Engineering · 10
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VERA-CS Modeling and Simulation of PWR Main Steam Line Break Core Response to DNB
2016 · Vefa N. Kucukboyaci, Yixing Sung, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 6
Benchmark of Subchannel Code VIPRE-W with PSBT Void and Temperature Test Data
2012 · Y. Sung, R. L. Oelrich, et al. · Science and Technology of Nuclear Installations · 6
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CASL COBRA-TF Improvements for PWR DNB Analysis.
2016 · Yixing Sung, Liping Cao, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
CASL L2 milestone report : VUQ.Y1.03, %22Enable statistical sensitivity and UQ demonstrations for VERA.%22
2011 · Yixing Sung, Brian Adams, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
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Departure from Nucleate Boiling (DNB) Predictive Modeling Using a Machine Learning Approach
2022 · Emre Tatli, Yixing Sung, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel) · 3
Use of Chromium Coating to Provide Protection of Zirconium Cladding at DNB Conditions
2022 · Zeses Karoutas, Dave Mitchell, et al. · TopFuel Light Water Reactor Fuel Performance Conference (TopFuel) · 2
Development of a Comprehensive Two-Phase Flow Database for the Validation of NEK-2P
2020 · Yang Liu, Univ. of Michigan, Ann Arbor, MI (United States), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2
COBRA-TF Simulation of Fuel Thermal Response During Reactivity Initiated Accidents Using the NSRR Pulse Irradiation Experiments
2014 · Vefa N. Kucukboyaci, Liping Cao, et al. · ASME International Mechanical Engineering Congress and Exposition (IMECE) · 2
AP1000 Plant CILC/CIPS Risk Assessment Using Advanced TH Methodology
2012 · G. Wang, P. Sapienza, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
Margin Assessment of AP1000 Loss of Flow Transient
2006 · Edward L. Carlin, Peter A. Hilton, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
Three Dimensional Analysis of 3-Loop PWR RCCA Ejection Accident for High Burnup
2006 · Cristian Marciulescu, Yixing Sung, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
VIPRE code void fraction prediction assessment using FRIGG loop data
2005 · Wang Guoqiang, Yixing Sung, et al. · 2
A New Approach to CHF Modeling Based on ML Technology for PWR Design Applications
2023 · Yixing Sung, Emre Tatli, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 1
CFD Analysis of Thermal Mixing and Mass Flux Distribution in the PWR After MSLB
2017 · Hong Xu, Yiban Xu, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
COBRA-TF Simulation of DNB Response During Reactivity-Initiated Accidents Using the NSRR Pulse Irradiation Experiments
2016 · Vefa N. Kucukboyaci, Liping Cao, et al. · Journal of Nuclear Engineering and Radiation Science · 1
Subchannel Thermal-Hydraulic Analysis at AP600 Low-Flow Steam-Line-Break Conditions
1995 · T. Morita, C. A. Olson, et al. · Nuclear Technology · 1
Utilization of AI/ML Technologies for Fuel Thermal-Hydraulic Methodology Development in Westinghouse
2025 · Emre Tatli, Yixing Sung, et al. · Nuclear Technology
VIPRE-W Benchmark With PSBT Void and Temperature Test Data
2024 · Sung, Yixing, Oelrich, Robert, et al. · Canadian Nuclear Society Proceedings
ANCKVIPRE Coupled Code Application to PWR Rod Withdrawal from Subcritical Event Analysis
2024 · Peter Hilton, Yixing Sung, et al. · International Conference on Physics of Reactors (PHYSOR)
Study of Effect of PWR Cold Leg Temperature Gradient on Reactor Core Condition
2022 · Emre Tatli, Vefa Kucukboyaci, et al. · International Conference on Physics of Reactors (PHYSOR)
Westinghouse Simplified RAVE™ Approach to PWR OT∆T/OP∆T Event Analyses
2022 · Peter Hilton, Yixing Sung, et al. · International Conference on Physics of Reactors (PHYSOR)
Works count: 29
Citation count: 130
H-index: 6
I10-index: 4
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