Author:
Kamaya Masayuki,Kawakubo Masahiro
Subject
Industrial and Manufacturing Engineering,Mechanical Engineering,Mechanics of Materials,General Materials Science,Modelling and Simulation
Reference25 articles.
1. Rules for construction of nuclear facility components – ASME boiler and pressure vessel code section III;ASME,2010
2. Japan Society of Mechanical Engineers, Codes for nuclear power generation facilities: rules on design and construction for nuclear power plants. JSME S NC1-2012; 2012.
3. Fatigue behavior of stainless steel 304L including strain hardening prestraining and mean stress effects;Colin;J Eng Mater Technol,2010
4. High-cycle fatigue behavior of type 316 stainless steel at 288°C including mean stress effect;Miura;Int J Fatigue,2006
5. Fatigue design criteria for pressure vessel alloys;Jaske;ASME J Press Ves Technol,1977
Cited by
72 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献