Advanced creep-fatigue evaluation rule for fast breeder reactor components: generalization of elastic follow-up model-Reference-Cited by-同舟云学术

Advanced creep-fatigue evaluation rule for fast breeder reactor components: generalization of elastic follow-up model

Published:1995-05 Issue:3 Volume:155 Page:499-518
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kasahara Naoto,Nagata Takashi,Iwata Koji,Negishi Hitoshi

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

Reference34 articles.

1. Design and Construction Rules for Mechanical Components of FBR Nuclear Island (RCC-MR);AFCEN,1985

2. ASME Code Case N-47-29;ASME,1990

3. Allowance for welds in elastic fatigue analysis—elastic follow up in welded structures;Barton,1991

4. The assessment of elastic follow-up in high temperature piping systems—overall survey and theoretical aspects;Boyle;Int. J. Press. Vess. Piping,1987

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