Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2I01-07] Stainless Steel

Thu. Sep 14, 2017 10:05 AM - 12:00 PM Room I (C310 - C Block)

Chair:Terumitsu Miura (INSS)

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10:05 AM - 10:20 AM

[2I01] FY2016 investigation for improvement of evaluation methods of irradiation effects on reactor pressure vessel and core internals

(1)Through-wall distribution of microstructure and mechanical property of irradiated JRQ material

*Tomohiro Kobayashi¹, Kenji Nishida¹, Masato Yamamoto¹ (1. CRIEPI)

10:20 AM - 10:35 AM

[2I02] FY2016 investigation for improvement of evaluation methods of irradiation effects on reactor pressure vessel and core internals

(2)Fracture toughness evaluation by miniature C(T) specimens on irradiated base metal and weld metal

*Masato Yamamoto¹, Yoshinori Hashimoto¹ (1. CRIEPI)

10:35 AM - 10:50 AM

[2I03] FY2016 investigation for improvement of evaluation methods of irradiation effects on reactor pressure vessel and core internals

(3)Characterization of microstructural change on neutron irradiated type 316L stainless steel

*Yuichi Miyahara¹, Kenji Nishida¹, Siwei Chen¹, Katsuhiko Fujii², Yuji Kitsunai³ (1. CRIEPI, 2. INSS, 3. NFD)

10:50 AM - 11:05 AM

[2I04] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(1)Summary

*Yutaka Watanabe¹, Toshiaki Horiuchi², Satoshi Minamoto³, Yoichi Takeda¹, Hiroshi Abe¹ (1. Tohoku University, 2. Hokkaido University of Science, 3. NIMS)

11:05 AM - 11:20 AM

[2I05] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(2)Thermal aging behavior of stainless steel welds

*Hiroshi ABE¹, Yutaka Watanabe¹, Yoichi Takada¹, Toshiaki Horiuchi², Satoshi Minamoto³ (1. Tohoku University, 2. Hokkaido University of Science, 3. NIMS)

11:20 AM - 11:35 AM

[2I06] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(3)Development of prediction model for G phase precipitation

*Toshiaki Horiuchi¹, Satoshi Minamoto², Hiroshi Abe³, Yoichi Takeda³, Yutaka Watanabe³ (1. Hokkaido University of Science, 2. National Institute for Materials Science, 3. Tohoku University)

11:35 AM - 11:50 AM

[2I07] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(4)Development of spinodal decomposition prediction model

*Satoshi Minamoto¹, Yutaka Watanabe², Youichi Takeda², Hiroshi Abe², Toshiaki Horiuchi³ (1. National Institute for Materials Science , 2. Tohoku Univ., 3. Hokkaido University of Science)

Time reserved for Chair (11:50 AM - 12:00 PM)

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