Oral presentation

[1I01-08] Radiation Effect

Wed. Sep 13, 2017 10:00 AM - 12:10 PM Room I (C310 - C Block)

Chair:Naoyuki Hashimoto (Hokkaido Univ.)

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10:00 AM - 10:15 AM

[1I01] Evaluation of irradiation effect for fracture toughness of austenitic stainless steel

*Tomonori Abe¹, Shigeaki Tanaka¹, Seiji Sakuraya², Tetsuya Toyota³, Takayuki Kaminaga⁴, Suguru Ooki⁴ (1. Toshiba Corporation, 2. Nippon Nuclear Fuel Development CO., Ltd., 3. Hitachi-GE Nuclear Energy, Ltd., 4. Tokyo Electric Power Company Holdings, Inc.)

10:15 AM - 10:30 AM

[1I02] Thermal and irradiation effect on microstracture of duplex stainless steel in BWR environment

*Shigeaki Tanaka¹, Tomonori Abe¹, Yuuji Kitsunai², Testuya Toyota³, Takayuki Kaminaga⁴, Suguru Ooki⁴ (1. Toshiba Corpration, 2. Nippon Nuclear Fuel Development Co., LTD., 3. Hitachi-GE Nuclear Energy, Ltd., 4. Tokyo Electric Power Company Holdings, Inc.)

10:30 AM - 10:45 AM

[1I03] Ion irradiation-induced microstructural changes in heat-affected zone of stainless weld overlay cladding of RPV steel

*Yoosung Ha¹, Hisashi Takamizawa¹, Satoshi Hanawa¹, Yutaka Nishiyama¹, Naoki Ebisawa², Takeshi Toyama², Yasuyoshi Nagai² (1. JAEA, 2. Tokoku Univ.)

10:45 AM - 11:00 AM

[1I04] Consideration of the correlation between microstructures and mechanical properties of irradiated austenitic stainless steels.

*Hitoshi Seto¹, Yuji Kitsunai¹, Masato Koshiishi¹, Shigeaki Tanaka², Tetsuya Toyota³, Takayuki Kaminaga⁴, Masaru Harada⁴, Suguru Ooki⁴ (1. NFD, 2. Toshiba, 3. Hitachi-GE, 4. TEPCO)

11:00 AM - 11:15 AM

[1I05] Electron-irradiation effects on diffusivity of Cu in Fe studied by 3D-AP

*Takeshi Toyama¹, Can Zhao¹, Masaki Shimodaira¹, Keiko Tomura¹, Koji Inoue¹, Yasuyoshi Nagai¹, Toshimasa Yoshiie¹ (1. IMR, Tohoku Univ.)

11:15 AM - 11:30 AM

[1I06] Measurement of diffusion coefficient of carbon in pure zirconium

*Teppei Otsuka¹, Tsuyoshi Matsumoto¹ (1. Faculty of Science and Engineering, KINDAI University)

11:30 AM - 11:45 AM

[1I07] Effect of Hydrogen Absorption and Irradiation on Microstructure and Mechanical Properties of Hafnium

*Kazuhiro Tsuchida¹, Mai Dung Thi Do¹, Kenta Murakami¹, Masahide Suzuki¹, Akihiro Iwase² (1. Nagaoka University of Technology, 2. Osaka Prefecture University)

11:45 AM - 12:00 PM

[1I08] Reserach and Development of RBWR for High Efficiency Transuranium Elements Burner

(4)Effects of ion irradiation on Zr alloys (2)

*Hideo Watanabe¹, Katsuhito Takahashi², Yusaku Maruno³ (1. Kyushu Univ.,, 2. NFD Co. Ltd., 3. Hitachi Ltd.)

Time reserved for Chair （12:00 PM - 12:10 PM）

Oral presentation

[1I09-14] Reactor Pressure VesselRPV

Wed. Sep 13, 2017 2:45 PM - 4:25 PM Room I (C310 - C Block)

Chair:Takeshi Toyama (Tohoku Univ.)

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2:45 PM - 3:00 PM

[1I09] Applicability advancement of probabilistic fracture mechanics for reactor pressure vessels

(1)Guideline on failure frequency calculation of Japanese reactor pressure vessels

*Yinsheng Li¹, Jinya Katsuyama¹, Kazuya Osakabe², shumpei uno² (1. Japan Atomic Energy Agency, 2. Mizuho Information & Research Institute)

3:00 PM - 3:15 PM

[1I10] Applicability advancement of probabilistic fracture mechanics for reactor pressure vessels

(2)Discussion on application of PFM into failure evaluation of reactor pressure vessels

*Jinya Katsuyama¹, Koichi Masaki¹, Yinsheng Li¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[1I11] Practicality advancement of probabilistic fracture mechanics for reactor pressure vessels

(3)Benchmark analysis for verification of probabilistic fracture mechanics analysis code PASCAL

*Koichi MASAKI¹, Shumpei Uno², Jinya Katsuyama¹, Yinsheng Li¹ (1. JAEA, 2. MHIR)

3:30 PM - 3:45 PM

[1I12] Multiscale Modeling of Irradiation Embrittlement of RPV steels

*Toshiki Nakasuji¹, Xiaoyong Ruan¹, Kazunori Morishita¹ (1. Kyoto university)

3:45 PM - 4:00 PM

[1I13] Effects of solute elements on microstructural change in ion-irradiated RPV model alloys

*Katsuhiko Fujii¹, Koji Fukuya¹ (1. Institute of Nuclear Safety System)

4:00 PM - 4:15 PM

[1I14] Development of reconstitution technology for RPV surveillance test specimen with electron beam welding

*Seiji Sakuraya¹, Yuji Kitsunai¹, Masato Koshiishi¹, Yasuo Morishima², Tetsuya Toyota³ (1. Nippon Nuclear Fuel Development Co.,LTD., 2. Toshiba Corpration, 3. Hitachi-GE Nuclear Energy, Ltd.)

Time reserved for Chair （4:15 PM - 4:25 PM）

Oral presentation

[1I15-20] Corrosion Behavior

Wed. Sep 13, 2017 4:25 PM - 6:05 PM Room I (C310 - C Block)

Chair:Hiroaki Abe (Univ. of Tokyo)

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4:25 PM - 4:40 PM

[1I15] Fundamental study on corrosion characteristics of wire-wrapped fuel cladding in lead-bismuth eutectic

*Yuhei Nakabo¹, Annette Heinzel², Alfons Weisenburger², Minoru Takahashi³, Masatoshi Kondo³ (1. Tokyo Institute of Technology, 2. Karlsruhe Institute of Technology, 3. Laboratory for Nuclear Energy)

4:40 PM - 4:55 PM

[1I16] Study on corrosion immunity of RPV inner welding

(1)Material characterization

*Hideki Yuya¹, Masataka Oyama¹, Jian Xu², Zihao Wang², yoichi takeda², tetsuo shoji² (1. Chubu Electric Power Company, 2. Tohoku University)

4:55 PM - 5:10 PM

[1I17] Tensile fracture behavior at grain boundary in irradiated stainless steels immersed in PWR primary water

*Terumitsu Miura¹, Takuya Fukumura¹, Katsuhiko Fujii¹, Koji Fukuya¹ (1. Instuitute of Nuclear Safety System)

5:10 PM - 5:25 PM

[1I18] Grain Boundary Oxidation Behavior of 19 dpa Neutron Irradiated Stainless Steels in Simulated PWR Water

*Takuya Fukumura¹, Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹, Yuji Kitsunai² (1. Institute of Nuclear Safety System, Inc., 2. Nuclera Fuel Development)

5:25 PM - 5:40 PM

[1I19] Long term thermal aging effect on the SCC initiation susceptibility of L-grade austenitic stainless steel

*Keietsu Kondo¹, So Aoki¹, Shinichiro Yamashita¹, Yoshiyuki Kaji¹, Masahiro Yamamoto¹ (1. JAEA)

5:40 PM - 5:55 PM

[1I20] Study on Applicability of Crack Growth Rate Models in IASCC Evaluations for BWR Internal Components

*Takahiro Hayashi¹, Tatsuya Kubo¹, Toshiyuki Saito¹ (1. TOSHIBA Corporation)

Time reserved for Chair （5:55 PM - 6:05 PM）

Oral presentation

[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）

Oral presentation

[2I08-17] SiC

Thu. Sep 14, 2017 2:45 PM - 5:25 PM Room I (C310 - C Block)

Chair:Hirotatsu Kishimoto (Muroran Inst. of Tech.)

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2:45 PM - 3:00 PM

[2I08] R&D for introducing silicon carbide materials to safety improvement of BWR's core

(1)Suppression of silica dissolution from SiC using corrosion resistant coating in simulated BWR environments

*Ryo Ishibashi¹, Takao Kondo¹, Shinichiro Yamashita² (1. Hitachi-GE Nuclear Energy, Ltd., 2. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[2I09] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(2)Plant transient analysis with SiC clad fuel

*Yutaka Takeuchi¹, Kazuo Kakiuchi¹, Sato Hisaki¹, Noriko Shirasu², Hiroaki Saito², Shinichiro Yamashita² (1. Toshiba Corporation, 2. JAEA)

3:15 PM - 3:30 PM

[2I10] Severe accident analysis for core fuel with SiC cladding

(1)Evaluation by severe accident analysis code MAAP

*Hideki Horie¹, Yutaka Takeuchi¹, Fumie Sebe¹, Kenya Takiwaki¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. Toshiba Corporation)

3:30 PM - 3:45 PM

[2I11] Severe accident analysis for core fuel with SiC cladding

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM

*Kenya Takiwaki¹, Yutaka Takeuchi¹, Hideki Horie¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. Toshiba Corporation)

3:45 PM - 4:00 PM

[2I12] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(1)Evaluations of influence on core neutronics characteristics

*Kazuya Yamaji¹, Kazuki Kirimura¹, Shinya Kosaka¹, Shinichiro Yamashita² (1. Mitsubishi Heavy Industries, Ltd., 2. Japan Atomic Energy Agency)

4:00 PM - 4:15 PM

[2I13] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(2)Study on fuel rod behavior during operation

*Kenichiro Furumoto¹, Hideyuki Teshima¹, Seiichi Watanabe¹, Teruhisa Yamamoto¹, Shinichiro Yamashita², Noriko Shirasu², Hiroaki Saito² (1. MNF, 2. JAEA)

4:15 PM - 4:30 PM

[2I14] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(3)Study on fuel behavior during design base accident

*Seiichi Watanabe¹, Hideyuki Teshima¹, Kenichiro Furumoto¹, Masaaki Katayama², Shinichiro Yamashita³ (1. MNF, 2. MHI, 3. JAEA)

4:30 PM - 4:45 PM

[2I15] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(4)Evaluations of severe accident tolerance for SiC

*Yoshinori Yamakoshi¹, Kazuki Kirimura¹, Shinya Kosaka¹, Shinichiro Yamashita² (1. Mitsubishi Heavy Industries, LTD., 2. Japan Atomic Energy Agency)

4:45 PM - 5:00 PM

[2I16] Microstructure and Strength Properties of Bonding Interface of NITE-SiC/SiC by Active Metal Brazing

*Atsuki Yoshihara¹, Naofumi nakazato¹, Joon-Soo Park², Chika Nogiwa¹, Hirotatsu Kishimoto¹ (1. Muroran Institute of Technology, 2. Organization of Advanced Sustainability Initiative for Energy System/Materials)

5:00 PM - 5:15 PM

[2I17] Role of irradiation defects in SiC on hydrothermal corrosion

*Sosuke Kondo¹, Yuki Maeda², Kazuhiro Fukami², Tatsuya Hinoki¹ (1. Institute of Advanced Energy, Kyoto University, 2. Department of Materials Science and Engineering, Kyoto University)

Time reserved for Chair （5:15 PM - 5:25 PM）

Oral presentation

[3M01-04] Advanced Material 1

Fri. Sep 15, 2017 10:50 AM - 11:55 AM Room M (N304 - N Block)

Chair:Sosuke Kondo (Kyoto Univ.)

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10:50 AM - 11:05 AM

[3M01] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(1)Overview of project

*Shinichiro Yamashita¹, Seiichi Watanabe², Kazuki Kirimura³, Kazuo Kakiuchi⁴, Takao Kondo⁵, Takashi Nozawa⁶, Kan Sakamoto⁷, Kazuyuki Kusagaya⁸, Shigeharu Ukai⁹, Akihiko Kimura¹⁰ (1. JAEA, 2. MNF, 3. MHI, 4. Toshiba, 5. Hitachi-GE, 6. QST, 7. NFD, 8. GNF-J, 9. Hokkaido Univ., 10. Kyoto Univ.)

11:05 AM - 11:20 AM

[3M02] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(2)FeCrAl-ODS steels for BWR fuel claddings

*Kan Sakamoto¹, Mutsumi Hirai¹, Shigeharu Ukai², Akihiko Kimura³, Akifumi akifumi⁴, Kazuyuki Kusagaya⁵, Takao Kondo⁶, Ikuo Ioka⁷, Shinichiro Yamashita⁷, Yoshiyuki Kaji⁷ (1. NFD, 2. Hokkaido Univ., 3. Kyoto Univ., 4. Waseda Univ., 5. GNF-J, 6. Hitachi GE, 7. JAEA)

11:20 AM - 11:35 AM

[3M03] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(3)SiC composite material for BWR

*Kazuo Kakiuchi¹, Hisaki Sato¹, Ryo Ishibashi², Takao Kondo², Ikuo Ioka³, Shinichiro Yamashita³, Yoshiyuki Kaji³ (1. Toshiba, 2. Hitachi GE, 3. JAEA)

11:35 AM - 11:50 AM

[3M04] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(4)SiC composite material for PWR

*Hideyuki Teshima¹, Seiichi Watanabe¹, Kenichiro Furumoto¹, Kazuki Kirimura², Yoshinori Yamakoshi², Ikuo Ioka³, Shinichiro Yamashita³, Yoshiyuki Kaji³ (1. MNF, 2. MHI, 3. JAEA)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral presentation

[3M05-10] Advanced Material 2

Fri. Sep 15, 2017 2:45 PM - 4:25 PM Room M (N304 - N Block)

Chair:Tamaki Shibayama (Hokkaido Univ.)

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2:45 PM - 3:00 PM

[3M05] R&D of advanced stainless steels for BWR fuel claddings (2)

(1)Applicability of core and fuel design

*Kazuyuki Kusagaya¹, Sho Takano¹, Daisuke Goto¹, Kan Sakamoto², Mutsumi Hirai², Shinichiro Yamashita³ (1. GNF-J, 2. NFD, 3. JAEA)

3:00 PM - 3:15 PM

[3M06] R&D of advanced stainless steels for BWR fuel claddings (2)

(2)Material performance during severe accidents

*Tomohiko Ikegawa¹, Ryo Ishibashi¹, Kan Sakamoto², Mutsumi Hirai², Shinichiro Yamashita³ (1. Hitachi-GE, 2. NFD, 3. JAEA)

3:15 PM - 3:30 PM

[3M07] R&D of advanced stainless steels for BWR fuel claddings (2)

(3)Mechanical properties of FeCrAl-ODS Steels

*Takashi Sowa¹, Shigeharu Ukai¹, Shigenari Hayashi¹, Naoko H Oono¹, Aghamiri Mohammad¹, Hiroki Shibata¹, Kan Sakamoto², Mutumi Hirai², Shinichiro yamashita³ (1. Hokkaido Univ., 2. NFD, 3. JAEA)

3:30 PM - 3:45 PM

[3M08] R&D of advanced stainless steels for BWR fuel claddings (2)

(4)Evaluation of irradiation behavior

*Naoyuki HASHIMOTO¹, Kodai TOYOTA², Kan SAKAMOTO³, Mutsumi HIRAI³, Shinichiro YAMASHITA⁴ (1. Faculty of Engineering, Hokkaido University, 2. Graduate school of Engineering, Hokkaido University, 3. NFD, 4. JAEA)

3:45 PM - 4:00 PM

[3M09] R&D of advanced stainless steels for BWR fuel claddings (2)

(5)Welding and inspection

*Akihiko Kimura¹, Sho Yuzawa¹, Kiyohiro Yabuuchi¹, Kan Sakamoto², Mutsumi Hirai², Shinichiro Yamashita³, Kazuyuki Kusagaya⁴ (1. IAE, Kyoto University, 2. NFD, 3. JAEA, 4. GNF-J)

4:00 PM - 4:15 PM

[3M10] R&D of advanced stainless steels for BWR fuel claddings (2)

(6)Tritium permeability and high temperature steam oxidation properties

*Katsuhito Takahahshi¹, Kan Sakamoto¹, Teppei Otsuka², Shigeharu Ukai³, Mutsumi Hirai¹, Shin-ichiro Yamashita⁴ (1. NFD, 2. Kinki Univ., 3. Hokkaido Univ., 4. JAEA)

Time reserved for Chair （4:15 PM - 4:25 PM）

Sessions

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

[1I01-08] Radiation Effect

(4)Effects of ion irradiation on Zr alloys (2)

[1I09-14] Reactor Pressure VesselRPV

(1)Guideline on failure frequency calculation of Japanese reactor pressure vessels

(2)Discussion on application of PFM into failure evaluation of reactor pressure vessels

(3)Benchmark analysis for verification of probabilistic fracture mechanics analysis code PASCAL

[1I15-20] Corrosion Behavior

(1)Material characterization

[2I01-07] Stainless Steel

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

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

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

(1)Summary

(2)Thermal aging behavior of stainless steel welds

(3)Development of prediction model for G phase precipitation

(4)Development of spinodal decomposition prediction model

[2I08-17] SiC

(1)Suppression of silica dissolution from SiC using corrosion resistant coating in simulated BWR environments

(2)Plant transient analysis with SiC clad fuel

(1)Evaluation by severe accident analysis code MAAP

(2)Evaluation by nuclear thermal hydraulics analysis code TRACTTM

(1)Evaluations of influence on core neutronics characteristics

(2)Study on fuel rod behavior during operation

(3)Study on fuel behavior during design base accident

(4)Evaluations of severe accident tolerance for SiC

[3M01-04] Advanced Material 1

(1)Overview of project

(2)FeCrAl-ODS steels for BWR fuel claddings

(3)SiC composite material for BWR

(4)SiC composite material for PWR

[3M05-10] Advanced Material 2

(1)Applicability of core and fuel design

(2)Material performance during severe accidents

(3)Mechanical properties of FeCrAl-ODS Steels

(4)Evaluation of irradiation behavior

(5)Welding and inspection

(6)Tritium permeability and high temperature steam oxidation properties

Authentication

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM