A Comparison Study of Creep-Fatigue Defect Growth Evaluations for a SFR IHTS Piping
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概要
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A defect behavior is one of the principal concerns to be dealt with for a structural integrity since defects may lead to the failure of a SFR(Sodium-cooled Fast Reactor) structure under high temperature loading conditions. A thin-walled and large diametric piping is adopted for the IHTS (Intermediate Heat Transport System) piping system of a SFR to enhance the system's economy and to reduce the thermal stress level. The structural material for the piping is Type 316 austenitic stainless steel. In this study, a defect growth evaluation of IHTS piping was performed for a semi-elliptical surface defect subjected to a combined mechanical loading and thermal loading of a high temperature above 500°C including a cyclic loading condition corresponding to a reactor refueling cycle. The creep-fatigue defect behavior evaluations were carried out by following the French Assessment Procedure A16, the UK Assessment Procedure R5 and the JNC procedure. The results were compared with each other and their strong and weak points were discussed. Also the degree of conservatism of each procedure was reviewed.
- 一般社団法人 日本機械学会の論文
著者
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PARK Chang-Gyu
Fast Reactor Development, Korea Atomic Energy Research Institute
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LEE Jae-Han
Fast Reactor Development, Korea Atomic Energy Research Institute
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KIM Jong-Bum
Fast Reactor Development, Korea Atomic Energy Research Institute