Oral presentation

[2J01-04] Reactor Pressure Vessel Steel

Tue. Mar 28, 2017 10:50 AM - 12:00 PM Room J (16-305 Building No.16)

Chair: Katsuhiko Fujii (INSS)

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10:50 AM - 11:05 AM

[2J01] Advanced Management of Irradiation Embrittlement of Reactor Pressure Vessel Steel

(1)3D-CFD and FEM analysis of Pressurized Thermal Shock Event in RPV Steel

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

11:05 AM - 11:20 AM

[2J02] Advanced Management of Irradiation Embrittlement of Reactor Pressure Vessel Steel

(2)Modeling of Nucleation Process of Defect Clusters in RPV Steel during Irradiation

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

11:20 AM - 11:35 AM

[2J03] Advanced Management of Irradiation Embrittlement of Reactor Pressure Vessel Steel

(3)Risk-based Maintenance of Reactor Pressure Vessel

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

11:35 AM - 11:50 AM

[2J04] Fracture evaluation of reactor pressure vessel steels using local approach technique

*Hisashi Takamizawa¹, Yoshihito Yamaguchi¹, Jinya Katsuyama¹, Yutaka Nishiyama¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[2J05-09] Fuel Cladding Tube 1

Tue. Mar 28, 2017 2:45 PM - 4:10 PM Room J (16-305 Building No.16)

Chair: Kazunori Morishita (Kyoto Univ.)

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2:45 PM - 3:00 PM

[2J05] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(1)Overall results

*Shigeharu Ukai¹, Naoko Oono¹, Kan Sakamoto², Tadahiko Torimaru², Takeji Kaito³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1. Hokkaido University, 2. Nippon Nuclear Fuel Development Co., LTD., 3. Japan Atomic Energy Agency, 4. Kyoto University, 5. Tokyo Institute of Technology)

3:00 PM - 3:15 PM

[2J06] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(2)Mechanical properties of FeCr- and FeCrAl-ODS steels at elevated temperature

*shoichi kato¹, Tomohiro Furukawa¹, Satoshi Ohtsuka¹, Yasuhide Yano¹, Toshihiko Inoue¹, Takeji Kaito¹, Akihiko Kimura², Tadahiko Torimaru³, Shigenari Hayashi⁴, Shigeharu Ukai⁵ (1. JAEA, 2. Kyoto Univ., 3. NFD, 4. Tokyo Institute of Technology Univ., 5. Hokkaido Univ.)

3:15 PM - 3:30 PM

[2J07] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(3)Formulation of failure life evaluation for FeCr- and FeCrAl-ODS steel claddings

*Yasuhide Yano¹, Soichi Kato¹, Satoshi Ohtsuka¹, Tomoyuki Uwaba¹, Yoshihiro Sekio¹, Toshihiko Inoue¹, Tomohiro Furukawa¹, Takeji Kaito¹, Shigeharu Ukai², Akihiko Kimura³ (1. Japan Atomic Energy Agency, 2. Hokkaido Univ., 3. Kyoto Univ.)

3:30 PM - 3:45 PM

[2J08] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(4)Analysis of microstructure at high temperatire

*Naoko Oono¹, Ken Nakamura¹, Ryoma Kamikawa¹, Shigeharu Ukai¹, Takeji Kaito², Tadahiko Torimaru³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1. Hokkaido Univ., 2. JAEA, 3. NFD, 4. Kyoto Univ., 5. Tokyo Tech.)

3:45 PM - 4:00 PM

[2J09] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(5)Evaluation on tolerance to failure of existing ODS ferritic steel claddings at the accident conditions of fast reactors

*Tomoyuki Uwaba¹, Yasuhide Yano¹, Satoshi yano.yasuhide@jaea.go.jp¹, Masayuki Naganuma¹, Takashi Tannno¹, Hiroshi Oka¹, Shoichi Kato¹, Takaji Kaito¹, Shigeharu Ukai², Akihiko Kimura³ (1. Japan Atomic Energy Agency, 2. Hokkaido University, 3. Kyoto University)

Time reserved for Chair （4:00 PM - 4:10 PM）

Oral presentation

[2J10-14] Fuel Cladding Tube 2

Tue. Mar 28, 2017 4:10 PM - 5:40 PM Room J (16-305 Building No.16)

Chair: Yoshitaka Matsukawa (Tohoku Univ.)

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4:10 PM - 4:25 PM

[2J10] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(6)Hot steam oxidation resistance of FeCrAl-ODS steels

*Toma Maeda¹, Shigeharu Ukai¹, Hiroki Shibata¹, Naoko Oono¹, Kan Sakamoto², Tadahiko Torimaru², Takeji Kaito³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1. Hokkaido university, 2. Nippon Nuclear Fuel Development, 3. Japan Atomic Energy Agency, 4. Kyoto university, 5. Tokyo Institute of Technology)

4:25 PM - 4:40 PM

[2J11] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(7)Thermal aging effects (Age-hardening/embrittlement)

*Kiyohiro Yabuuchi¹, Akihiko Kimura¹, Tadahiko Torimaru², Takeji Kaito⁴, Shigenari Hayashi⁵, Naoko Oono³, Shigeharu Ukai³ (1. IAE, Kyoto Univ., 2. NFD, 3. Hokkaido Univ., 4. JAEA, 5. Tokyo Institute of Technology)

4:40 PM - 4:55 PM

[2J12] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(8)a/a¢ phase separation effects (Evaluation summary)

Akihiko Kimura¹, *Kiyohiro Yabuuchi¹, Tadahiko Torimaru², Shigeharu Ukai³, Naoko Oono³, Takeji Kaito⁴, Shigenari Hayashi⁵ (1. IAE, Kyoto University, 2. NFD, 3. Hokkaido University, 4. JAEA, 5. TIT)

4:55 PM - 5:10 PM

[2J13] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(9)High temperature reaction with UO₂, LOCA simulation test

*Tadahiko Torimaru¹, Kan Sakamoto¹, Shigeharu Ukai², Naoko Oono², Takeji Kaito³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1. NFD, 2. Hokkaido Univ., 3. JAEA, 4. Kyoto Univ., 5. Tokyo Tech Univ.)

5:10 PM - 5:25 PM

[2J14] R&D of ODS ferritic steel cladding for maintaining fuel integrity at accident condition (3)

(10)Applicability to LWR fuel claddings

*Kan Sakamoto¹, Tadahiko Torimaru¹, Shigeharu Ukai², Naoko Oono², Takeji Kaito³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1. NFD, 2. Hokkaido Univ., 3. JAEA, 4. Kyoto Univ., 5. Tokyo Institute of Technology)

Time reserved for Chair （5:25 PM - 5:35 PM）

Oral presentation

[2J15-17] Fuel Cladding Tube 3

Tue. Mar 28, 2017 5:40 PM - 6:30 PM Room J (16-305 Building No.16)

Chair: Terumitsu Miura (INSS)

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5:40 PM - 5:55 PM

[2J15] Development of Corrosion Resistant Coating Technology to Silicon Carbide Fuel Materials

*Ryo Ishibashi¹, Shinya Okamoto¹, Kazushige Ishida³, Takao Kondo², Katsumasa Miyazaki¹ (1. Center for Technology Innovation - Materials, Research & Development Group, Hitachi, Ltd., 2. Hitachi-GE Nuclear Energy, Ltd, 3. Center for Technology Innovation - Energy, Research & Development Group, Hitachi, Ltd.)

5:55 PM - 6:10 PM

[2J16] Progress on ATF Development of SiC for LWR

Improvement of Corrosion Resistance

*Masayuki Uchihashi¹, Masaru Ukai¹, Shoko Suyama¹, Kazuo Kakiuchi¹, Takashi Takagi², Akihide Kawaguchi² (1. Toshiba Corporation, 2. IBIDEN CO.,LTD.)

6:10 PM - 6:25 PM

[2J17] Development of in cell biaxial testing device for nuclear fuel claddings

*Masafumi Nakatsuka¹, Kan Sakamoto², Masaki Aomi³ (1. Zirkotechnology, 2. Nippon Nuclear Fuel Development Co.,Ltd, 3. Global Nuclear Fuel Japan )

Time reserved for Chair （6:25 PM - 6:30 PM）

Oral presentation

[3J01-04] Irradiation Effect

Wed. Mar 29, 2017 9:30 AM - 10:35 AM Room J (16-305 Building No.16)

Chair: Naoyuki Hashimoto (Hokkaido Univ.)

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9:30 AM - 9:45 AM

[3J01] Nucleation and Growth of Defect Clusters during In-situ Irradiation of Stainless Steels with Considerations of Surface Effects

*Dongyue Chen¹, Kenta Murakami², Naoto Sekimura¹ (1. The University of Tokyo, Department of Nuclear Engineering and Management, School of Engineering, 2. The University of Tokyo, Nuclear Professional School, School of Engineering)

9:45 AM - 10:00 AM

[3J02] Solute cluster formation of ion-irradiated Fe-Mn-(Ni, Si) alloys

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

10:00 AM - 10:15 AM

[3J03] Microstructure and hardening of ion-irradiated heat-affected zone of reactor pressure vessel steel

*Yoosung Ha¹, Hisashi Takamizawa¹, Jinya Katsuyama¹, Yutaka Nishiyama¹, Kenta Yoshida², Takeshi Toyama², Yasuyoshi Nagai² (1. JAEA, 2. Tohoku Univ.)

10:15 AM - 10:30 AM

[3J04] Discussion on Irradiation Resistance of Composition-Adjusted Austenitic Stainless Steels with High Cr Concentration for Reactor Pressure Vessel Internals

*Yun Wang¹ (1. Hitachi Ltd.)

Time reserved for Chair （10:30 AM - 10:35 AM）

Oral presentation

[3J05-09] Pressure Vessel Materials

Wed. Mar 29, 2017 10:35 AM - 12:00 PM Room J (16-305 Building No.16)

Chair: Kan Sakamoto (NFD)

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10:35 AM - 10:50 AM

[3J05] Consideration of an evaluation method of solution atom clusters in ferrite phase by EDS tomography

*Hitoshi Seto¹, Yuji Kitsunai¹, Tetsushi Yamaoka², Tetsuya Toyota³ (1. Nippon Nuclear Fuel Development (NFD), 2. Toshiba, 3. Hitachi GE)

10:50 AM - 11:05 AM

[3J06] On-the-fly kinetic Monte Carlo for a conservative climb of a cluster of self-interstitial atoms in BCC-Fe

*Sho Hayakawa¹, Taira Okita², Mitsuhiro Itakura³, Haixuan Xu⁴, Yuri N. Osetsky⁵ (1. School of Engineering, the University of Tokyo, 2. Research into Artifacts, Center for Engineering, the University of Tokyo, 3. Japan Atomic Energy Agency, 4. The University of Tennessee, Knoxville, 5. Oak Ridge National Laboratory)

11:05 AM - 11:20 AM

[3J07] A study of low-temperature irradiation embrittlement of carbon steel

*Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹, Masahiro Kawakubo² (1. Instuitute of Nuclear Safety System, 2. Radioactive Waste Management Funding and Research Center)

11:20 AM - 11:35 AM

[3J08] Performance of Oxygen Sensors with Solid Fe/Fe₃O₄ and Liquid Bi/Bi₂O₃ Reference Electrode in Liquid LBE

*Pribadi Mumpuni Adhi¹, Masatoshi Kondo², Minoru Takahashi² (1. Department of Nuclear Engineering, Tokyo Institute of Technology, 2. Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology)

11:35 AM - 11:50 AM

[3J09] Effect of Hydrogen on the Material Property of Hafnium

*Yasuharu Kawahara¹, Thi Mai Dung Do¹, Masahide Suzuki¹, Akihiro Iwase², Ryutaro Kimura^3,1 (1. Nagaoka University of Technology Nuclear System Safety Engineering, 2. Osaka Prefecture University, 3. Currently Japan Nuclear Fuel Limited)

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

Oral presentation

[3J10-15] Zirconium Alloys

Wed. Mar 29, 2017 2:45 PM - 4:15 PM Room J (16-305 Building No.16)

Chair: Naoko Oono (Hokkaido Univ.)

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2:45 PM - 3:00 PM

[3J10] Oxidation process of Nb precipitates in the surface oxide layer of J-AlloyTM subjected to corrosion in PWR-simulated water

*Yoshitaka Matsukawa¹, Shuhei Kitayama¹, Kenta Murakami², Yasunari Shinohara³, Kenta Yoshida¹, Huilong Yang², Takeshi Toyama¹, Hiroaki Muta⁴, Shinsuke Yamanaka⁴, Hiroaki Abe² (1. Tohoku University, Institute for Materials Research, 2. The University of Tokyo, 3. NDS, 4. Osaka University)

3:00 PM - 3:15 PM

[3J11] Effects of thermo-mechanical history on the composition of bcc precipitates in Zr-2.5Nb alloys

*Ippei Ohkuma¹, Yoshitaka Matsukawa¹, Hiroaki Muta², Huilong Yang³, Takeshi Toyama¹, Shinsuke Yamanaka², Yuhki Satoh¹, Hiroaki Abe³ (1. Tohoku University, 2. Osaka University, 3. The University of Tokyo)

3:15 PM - 3:30 PM

[3J12] Effects of 140 MeV C⁴⁺ irradiation on microstructure and mechanical properties in Zr-1.8Nb alloys

*Huilong Yang¹, Sho Kano¹, Zhengang Duan³, Yoshitaka Matsukawa², Kenta Murakami¹, Hiroaki Abe¹ (1. Graduate School of Engineering, The University of Tokyo, 2. Institute for Materials Research, Tohoku University, 3. Graduate School of Engineering, Tohoku University)

3:30 PM - 3:45 PM

[3J13] The hardness value evaluation with hydride generations in Zr by the nano-indentation hardness test and dynamic microstructure observation

*Kouichi Tougou¹, Takashi Onitsuka¹, Kaoru Tone¹, Naohiro Shimomura¹, Ken-ichi Fukumoto¹, Masayoshi Uno¹, Hiroaki Muta² (1. University of Fukui, 2. Osaka University)

3:45 PM - 4:00 PM

[3J14] Research and Development of RBWR for High Efficiency Transuranium Elements Burner

(2)Effects of ion irradiation on Zr alloys

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

4:00 PM - 4:15 PM

[3J15] Research and Development of RBWR for High Efficiency Transuranium Elements Burner

(3)First-principles calculation of interaction between solute atoms and irradiation defects in Zr

*Mitsuhiro Itakura¹, Taira Okita² (1. JAEA, 2. Univ. Tokyo)

Sessions

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

[2J01-04] Reactor Pressure Vessel Steel

(1)3D-CFD and FEM analysis of Pressurized Thermal Shock Event in RPV Steel

(2)Modeling of Nucleation Process of Defect Clusters in RPV Steel during Irradiation

(3)Risk-based Maintenance of Reactor Pressure Vessel

[2J05-09] Fuel Cladding Tube 1

(1)Overall results

(2)Mechanical properties of FeCr- and FeCrAl-ODS steels at elevated temperature

(3)Formulation of failure life evaluation for FeCr- and FeCrAl-ODS steel claddings

(4)Analysis of microstructure at high temperatire

(5)Evaluation on tolerance to failure of existing ODS ferritic steel claddings at the accident conditions of fast reactors

[2J10-14] Fuel Cladding Tube 2

(6)Hot steam oxidation resistance of FeCrAl-ODS steels

(7)Thermal aging effects (Age-hardening/embrittlement)

(8)a/a¢ phase separation effects (Evaluation summary)

(9)High temperature reaction with UO2, LOCA simulation test

(10)Applicability to LWR fuel claddings

[2J15-17] Fuel Cladding Tube 3

Improvement of Corrosion Resistance

[3J01-04] Irradiation Effect

[3J05-09] Pressure Vessel Materials

[3J10-15] Zirconium Alloys

(2)Effects of ion irradiation on Zr alloys

(3)First-principles calculation of interaction between solute atoms and irradiation defects in Zr

Authentication

(9)High temperature reaction with UO₂, LOCA simulation test