共 50 条
- [42] 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):
- [43] Study on the Characteristics of Effective Delayed Neutron Fraction (βeff) for Pebble-Bed Reactor with Plutonium Fuel Iranian Journal of Science and Technology, Transactions A: Science, 2019, 43 : 3037 - 3045
- [46] Study on the Characteristics of Effective Delayed Neutron Fraction (βeff) for Pebble-Bed Reactor with Plutonium Fuel IRANIAN JOURNAL OF SCIENCE AND TECHNOLOGY TRANSACTION A-SCIENCE, 2019, 43 (A6): : 3037 - 3045
- [47] EXPERIMENTAL RESEARCH OF PEBBLE DYNAMICS OF TWO-REGION REACTOR CORE IN HTR PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 6, 2011, : 115 - 118
- [48] Research on Pneumatic Transportation of Fuel Elements in Pebble Bed Reactor 2012 ASIA-PACIFIC POWER AND ENERGY ENGINEERING CONFERENCE (APPEEC), 2012,
- [49] A THREE-DIMENSIONAL RIGID-BODY MODEL FOR SEISMIC ANALYSIS OF THE PEBBLE-BED HTR GRAPHITE CORE STRUCTURE PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 2, 2014,
- [50] RETRIEVING FUEL ELEMENTS BY PNEUMATIC SUCTION IN PEBBLE-BED HIGH TEMPERATURE GAS-COOLED REACTOR PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,