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- [42] Transient Detection and Identification for HTR-PM Based on Principle Component Analysis NUCLEAR POWER PLANTS: INNOVATIVE TECHNOLOGIES FOR INSTRUMENTATION AND CONTROL SYSTEMS, 2018, 455 : 65 - 72
- [44] TRANSIENT ANALYSIS OF ACTIVE RESIDUAL HEAT REMOVAL PROCESS FOR HTR-PM PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,
- [46] HTR-PM SIMULATION ANALYSIS OF ACCIDENT CONDITIONS BASED ON VPOWER PLATFORM PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 6, 2014,
- [48] STUDY ON REACTOR CAVITY COOLING SYSTEM OF HTR-PM IN DLOFC ACCIDENT WITH TIN-CAVCO CODE AND SPECTRA CODE PROCEEDINGS OF 2024 31ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 6, ICONE31 2024, 2024,
- [49] Numerical simulation of hot gas mixing with leakage flow at HTR-PM reactor core outlet (1) Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education, Tsinghua University, Beijing; 100084, China; (2) School of Aerospace, Tsinghua University, Beijing; 100084, China, 1600, et al.; GLSEQ, LLC/SCI Technologies. Inc; Hitachi-GE Nuclear Energy, Ltd.; Mitsubishi Heavy Industries, Ltd. (MHI); Toshiba Corporation; Westinghouse Electric Company (American Society of Mechanical Engineers (ASME), United States):