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Development of structural integrity assessment guideline for FBR components
Various thermal transients may produce harmful damage to high-temperature components of a Fast Breeder Reactor (FBR) plant. As fundamental tools for the long-term integrity assessments of them, accurate inelastic analysis method and creep-fatigue life estimation method were developed for low-carbon medium-nitrogen type 316 stainless steel which is planned to be used in the future FBR plants in Japan. Incorporating the results of additional investigation, a guideline for the assessment of FBR components was developed. The guideline includes the limitation of inelastic strain and creep-fatigue damage assessment method for base metal and welded joints. Results of evaluation of structural model failure tests showed that sufficient margin can be kept by the assessment according to the guideline which includes safety factors.
Development of structural integrity assessment guideline for FBR components
Various thermal transients may produce harmful damage to high-temperature components of a Fast Breeder Reactor (FBR) plant. As fundamental tools for the long-term integrity assessments of them, accurate inelastic analysis method and creep-fatigue life estimation method were developed for low-carbon medium-nitrogen type 316 stainless steel which is planned to be used in the future FBR plants in Japan. Incorporating the results of additional investigation, a guideline for the assessment of FBR components was developed. The guideline includes the limitation of inelastic strain and creep-fatigue damage assessment method for base metal and welded joints. Results of evaluation of structural model failure tests showed that sufficient margin can be kept by the assessment according to the guideline which includes safety factors.
Development of structural integrity assessment guideline for FBR components
Takahashi, Y. (author)
1998
8 Seiten, 15 Quellen
Conference paper
English
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