Creep–fatigue evaluation method for weld joints of Mod.9Cr–1Mo steel. Part I: Proposal of the evaluation method based on finite element analysis and uniaxial testing

Author:

Ando Masanori,Takaya Shigeru

Funder

JAEA

METI

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference19 articles.

1. Ando, M., Watanabe, S., Kikuchi, K., Otani, T., Satoh, K., Tsukimori, K., Asayama, T., 2013. Development of 2012 Edition of JSME Code for Design and Construction of Fast Reactors (6) Design margin assessment for the new materials to the rules. In: Proceedings of ASME 2013 Pressure Vessels and Piping Division Conference, PVP2013-97803.

2. Comparison and assessment of the creep-fatigue evaluation methods with notched specimens made of Mod. 9Cr-1Mo steel;Ando;J. Pressure Vessel Technol.,2014

3. Design study and R&D progress on Japan sodium-cooled fast reactor;Aoto;J. Nucl. Sci. Technol.,2011

4. Asayama, T., Hasebe, S., Hirakawa, Y., Wada, Y., 1993. Creep-fatigue evaluation method for Mod. 9Cr-1Mo weldment. Trans. Struct. Mech. Reactor Technol., L05/5, 123–128.

5. ASME Boiler and Pressure Vessel Code Section III, Subsection NH,2012

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