SB-03-2(100) Benchmark Study of Creep-Fatigue life Predicted by Elevated Temperature Design Standards of Every Country(Materials Performance in Nuclear Application 3)

概要

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Elevated Temperature Design Standards have been developed in many countries to be applied for the designing of Fast Breeder Reactor components. Dominant failure mode considered in these standards is creep-fatigue crack initiation. This paper presents a comparison among creep-fatigue lives predicted by representative design codes. DDS in Japan, ASME Sec. III-NH in USA, R5 in UK and RCC-MR in France were adopted into the four kinds of benchmark problems. The first problem is smooth cylinder subjected to axial temperature distribution. The second one is upper ring plate in reactor vessel. The third is upper tube-sheet of intermediate heat exchanger (IHX). The fourth is z-shaped junction in IHX. The first problem is the experiment with 10hrs hold time to verify the current design standard. Predicted creep-fatigue lives were compared with the crack initiation lives measured in experiment. The other problems were examples of FBR design with hold period of several hundreds hours. Estimated lives show wide scatter larger than a hundred times. Reasons to cause scatter were also discussed.
一般社団法人日本機械学会の論文
2001-06-03