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Report No.
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Development of elevated temperature structural design method for fast reactor vessels, 1; Concept of development in strength evaluation

Kawasaki, Nobuchika ; Nagae, Yuji ; Kato, Shoichi ; Ando, Masanori ; Kasahara, Naoto

Concept of development in strength evaluation for fast reactor vessels was introduced. Based on the characteristics of reactor vessel for developing fast breeder reactor, creep-fatigue strength and ratcheting deformation criterion are under developing. For the creep-fatigue strength, intermediate dwelling creep-fatigue, aging effect and strain concentration are selected as developing items. The ratcheting deformation criterion will be determined by ratcheting fatigue and ratcheting creep-fatigue test results.

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