Division 6: Design Issues, Codes and Standards

[Tu.2.C] Creep / Fatigue Design and Flaw Evaluation (1)

Tue. Mar 5, 2024 10:55 AM - 11:55 AM 313 (Conference Center 3F)

Chair:Kiminobu Hojo(Mitsubishi Heavy Industries)
Co-Chair:Stephane Chapuliot(EDF)

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10:55 AM - 11:15 AM

[Tu.2.C-01] Influence of plastic strain on fatigue damage assessment for seismic load (K_s factors for an actual piping system of nuclear power plant)

*masayuki kamaya¹ (1. Institute of Nuclear Safety System, Inc.)

11:15 AM - 11:35 AM

[Tu.2.C-02] Fracture Mechanics Assessment of the Steam-Generator Tube-Sheet plate through a
J-Q approach for consideration of the constraint loss

*Stephane Chapuliot¹, Aurore Parrot¹, Olivier Ancelet², Stephane Marie² (1. EDF/R&D, 2. FRAMATOME)

11:35 AM - 11:55 AM

[Tu.2.C-03] Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

*Yasuto Nagoshi¹, Takuya Fukahori¹, Hiroshi Okada², Akiyuki Takahashi², Masaki Shimodaira³, Takashi Ueda⁴, Takuya Ogawa⁵, Kenji Yashirodai⁶, Yukio Takahashi⁷, Mitsuru Ohata⁸ (1. Mitsubishi Heavy Industries, Ltd., 2. Tokyo University of Science, 3. Japan Atomic Energy Agency, 4. IHI Corporation, 5. Toshiba Energy Systems & Solutions Corporation, 6. Hitachi, LTD., 7. Central Research Institute of Electric Power Industry, 8. Osaka University)

Session information

[Tu.2.C] Creep / Fatigue Design and Flaw Evaluation (1)

[Tu.2.C-01] Influence of plastic strain on fatigue damage assessment for seismic load (K_s factors for an actual piping system of nuclear power plant)

[Tu.2.C-02] Fracture Mechanics Assessment of the Steam-Generator Tube-Sheet plate through a
J-Q approach for consideration of the constraint loss

[Tu.2.C-03] Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

Authentication

Session information

[Tu.2.C] Creep / Fatigue Design and Flaw Evaluation (1)

[Tu.2.C-01] Influence of plastic strain on fatigue damage assessment for seismic load (Ks factors for an actual piping system of nuclear power plant)

[Tu.2.C-02] Fracture Mechanics Assessment of the Steam-Generator Tube-Sheet plate through aJ-Q approach for consideration of the constraint loss

[Tu.2.C-03] Benchmark Analysis by Beremin Model and GTN Model in CAF Subcommittee

Authentication

[Tu.2.C-01] Influence of plastic strain on fatigue damage assessment for seismic load (K_s factors for an actual piping system of nuclear power plant)

[Tu.2.C-02] Fracture Mechanics Assessment of the Steam-Generator Tube-Sheet plate through a
J-Q approach for consideration of the constraint loss