Division 2: Fracture Mechanics and Structural Integrity

[Tu.2.I] Structural Integrity Assessment of Reactor Pressure Vessel (2)

2024年3月5日(火) 10:55 〜 12:15 415 (Conference Center 4F)

Chair:Mark Kirk(PEAI Consulting/ Central Research Institute of Electric Power Industry)
Co-Chair:Yoosung Ha(Japan Atomic Energy Agency)

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10:55 〜 11:15

[Tu.2.I-01] Influence of the maximum fatigue-pre-cracking load on Master Curve T0 evaluation concerning the warm-pre-stress effect

*Masato Yamamoto¹, Daiki Takagoshi², Takatoshi Hirota², Mark Kirk¹ (1. Central Research Institute of Electric Power Industry, 2. Mitsubishi Heavy Industry)

11:15 〜 11:35

[Tu.2.I-02] Investigation of the Master Curve Concept for Ferritic Ductile Cast Iron

*Marcel Holzwarth¹, Uwe Mayer¹, Wolfram Baer², Stefan Weihe¹ (1. Materials Testing Institute University of Stuttgart (MPA), 2. Federal Institute for Materials Research and Testing (BAM))

11:35 〜 11:55

[Tu.2.I-03] Applicability of Master Curve Method using Miniature C(T) specimen to Japanese Reactor Pressure Vessel Steels

*Tomoki Shinko¹, Tetsuya Toyota¹, Ryoichi Saeki¹ (1. Central Research Institute of Electric Power Industry)

11:55 〜 12:15

[Tu.2.I-04] Research on the pressure-temperature curve of reactor pressure vessel and its key parameters

*Juan Luo¹, Jiacheng Luo¹ (1. Nuclear Power Institute of China)

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