THERMAL-HYDRAULICS

作品数:17被引量:23H指数:3
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相关领域:核科学技术更多>>
相关机构:清华大学更多>>
相关期刊:《Plasma Science and Technology》《Tsinghua Science and Technology》《Annual Report of China Institute of Atomic Energy》《Applied Mathematics》更多>>
相关基金:国家自然科学基金中国博士后科学基金更多>>
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Feasibility of an innovative long-life molten chloride-cooled reactor被引量:2
《Nuclear Science and Techniques》2020年第4期1-15,共15页Ming Lin Mao-Song Cheng Zhi-Min Dai 
This work was supported by Strategic Pilot Science and Technology Project of Chinese Academy of Sciences(No.XD20191031).
Molten salt-cooled reactor is one of the six GenIV reactors with promising characteristics including safety,reliability,proliferation resistance,physical protection,economics,and sustainability.In this paper,a small i...
关键词:MOLTEN salt-cooled REACTOR NEUTRONICS Radiation damage THERMAL-HYDRAULICS 
Development of a dynamics model for graphite-moderated channel-type molten salt reactor被引量:3
《Nuclear Science and Techniques》2019年第1期145-155,共11页Long He Cheng-Gang Yu Rui-Min Ji Wei Guo Ye Dai Xiang-Zhou Cai 
supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000);the Frontier Science Key Program of the Chinese Academy of Sciences(No.QYZDY-SSW-JSC016);the National Natural Science Foundation of China Key Program(No.91326201)
A molten salt reactor(MSR) is one of the six advanced reactor concepts selected by the generation Ⅳ international forum because of its advantages of inherent safety, and the promising capabilities of Th-U breeding an...
关键词:MOLTEN SALT REACTOR THERMAL-HYDRAULICS Point REACTOR model Thermal coupling 
Numerical Simulations of Upper Plenum Thermal-Hydraulics of Monju Reactor Vessel Using High Resolution Mesh Models
《Journal of Energy and Power Engineering》2013年第4期679-688,共10页Hiroaki Ohira Kei Honda Masutake Sotsu 
In order to evaluate the effects of the FHs (flow holes) on the inner barrel, which were installed in the upper plenum of the Monju reactor vessel, a high resolution meshes around the FHs was constructed. Using this...
关键词:Monju reactor vessel upper plenum THERMAL-HYDRAULICS numerical simulation flow holes. 
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