Thermal hydraulic challenges in fast reactor design. In: Keynote Paper KN10, Proceedings of the 12th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Pittsburgh, PA, USA, September 2007.Todreas, N., 2007, "Thermal Hydraulic Challenges in Fast Reactor Design," Proceedings...
当当中华商务进口图书旗舰店在线销售正版《海外直订Nuclear Reactor Thermal-Hydraulics: Past, Present and Future 核反应堆热工水力学:过去,现在和未来》。最新《海外直订Nuclear Reactor Thermal-Hydraulics: Past, Present and Future 核反应堆热工水力学:过去,现在和
WORTH workshop are to bring together researchers, regulators, and designers from industries, laboratories and academia, active in the area of nuclear reactor thermal-hydraulics as well as in the field of severe accident, to present the state-of-the-art technologies, to exchange their expertise ...
Correlations for the interfacial drag force are proposed. Some illustrative examples of application (including also...doi:10.1080/00295450.2017.1316660StevanovicVladimir DNuclear technology
Third International Conference on Reactor Thermal Hydraulics : Newport, Rhode Island, USA, October 15–18, 1985学术研讨会会议综述16世纪岭南地区摘要:黄国信中山大学历史系Nuclear Engineering and Design
Thermal-hydraulicsOptimizationChina has proposed several concepts of breeder blanket for future fusion reactor, one of which is the helium-cooled pebble bed (HCPB) blanket. HCPB blanket is a cellular design with solid breeder units (BUs) and other structural components to achieve its functional ...
Thermal Hydraulics Studies for a Molten Salt Burner Reactor S. Wang, A. Rineiski, W. Maschek Forschungszentrum Karlsruhe Institute for Nuclear and Energy Technologies Postfach 3640, D-76021 Karlsruhe Germany Abstract Molten Salt Reactors (MSRs) can be charged with Pu, minor actinides (MAs) and ...
The objectives of the WORTH workshop are to bring together researchers, regulators, and designers from industries, laboratories and academia, active in the area of nuclear reactor thermal-hydraulics as well as in the field of severe accident, to present the state-of-the-art technologies, to ...
Thermal hydraulics analysis of the Advanced High Temperature Reactor The Advanced High Temperature Reactor (AHTR) is a liquid salt-cooled nuclear reactor design concept, featuring low-pressure molten fluoride salt coolant, a carbon composite fuel form with embedded coated particle fuel, passively trigger...
A kinetics and thermal hydraulics capability for the analysis for research reactor ANL (1983) Google Scholar Cited by (0) © 2018 Korean Nuclear Society, Published by Elsevier Korea LLC. Recommended articles cannot be displayed at this time. ...