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[61]Benchmark Validation of SPRUCE2.0 for Severe-Accident Core Thermal-Hydraulic Behavior
HAO WU Master Student Harbin Engineering University
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[60]AI-Based Multi-Step Source-Term Estimation for Nuclear Emergency Decision Support: A Comparative Assessment of GRU and PatchTST
Qaisar Nadeem Lecturer Pakistan Institute of Engineering & Applied Sciences
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[59]Load Following Control of Nuclear Reactor Core Using Optimized T-S Fuzzy PI Controller Based on Validated Nonlinear Two-point Kinetics Model
Dr. Hailemichael Guadie Mengsitu Doctoral Researcher Harbin Engineering University
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[58]Techno-Economic Assessment of HTGR–SOEC Coupling for High-Efficiency Hydrogen Production
Muhammad Zaman Professor Department of Chemical Engineering, PIEAS
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[55]Heat-Pipe Reactor–sCO2 Control Based on Safety-Constrained Reinforcement Learning Method under Abnormal Transients
Gerson Kondo PhD Student Harbin Engineering University
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重要日期
  • 会议日期

    10月30日

    2026

    至

    11月01日

    2026

  • 09月30日 2026

    初稿截稿日期

主办单位
Harbin Engineering University
State Key Laboratory of Marine Thermal Energy and Power
Heilongjiang Nuclear Society
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