Creep-fatigue crack behaviour of a mod. 9Cr-1Mo steel structure with weldments

Author:

Lee Hyeong-Yeon,Kim Jong-Bum,Kim Woo-Gon,Lee Jae-Han

Publisher

Springer Science and Business Media LLC

Reference17 articles.

1. Hahn, D-H et. al., KALIMER-600 Conceptual Design Report, KAERI/TR-3381, Korea Atomic Energy Research Institute, Daejeon, (2007).

2. ASME Boiler and Pressure Vessel Code, Section III, Rules for Construction of Nuclear Power Plant Components, Div. 1, Subsection NH, Class 1 Components in Elevated Temperature Service, ASME; (2007).

3. RCC-MR, Section I Subsection B, Design and Construction Rules for Mechanical Components of Nuclear Installations, 2007 Edition, AFCEN; (2007).

4. High temperature structural design guideline for fast breeder demonstration reactor (draft), JAPC, (1999).

5. RCC-MR, Section I Subsection Z, Technical Appendix 16, Design and Construction Rules for Mechanical Components of Nuclear Installations, 2007 Edition, AFCEN, (2007).

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