Author:
Niu Fenglei,Tian Li,Yu Yu,Li Rizhu,Norman Timothy L.
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference17 articles.
1. Development of components for the gas-cooled fast breeder reactor program;Dee;Nuclear Engineering and Design,1977
2. Gas pressure test of THTR steam generators;Elter;International Journal of Pressure Vessels and Piping,1986
3. Flow Instability Analysis of 10MW High Temperature Gas-cooled Test Reactor Steam Generator;Fenglei,1997
4. Heat Transfer and Fluid Flow in Nuclear System;Henri Fenech,1981
5. Experiment and verification test of the once-through steam generator of the 10MW high-temperature gas-cooled reactor – flow stability of the once-through steam generator;Huaiming;Nuclear Science and Technology,2004
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17 articles.
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