Oral Presentation

[1H01-08] Pb-Bi/SiC-1

Sat. Mar 26, 2016 10:00 AM - 12:00 PM Room H (Lecture Rooms B B204)

Chair: Takashi Nozawa (JAEA)

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10:00 AM - 10:15 AM

[1H01] Research and development of innovative technologies for nuclear reactor core
material with enhanced safety

(1)Development and evaluation of SiC material for nuclear reactor core applica
tion

＊Tatsuya Hinoki¹, Fumihisa Kano², Yoshihiro Hyodo² (1.Kyoto University, 2.TOSHIBA Corporation)

10:15 AM - 10:30 AM

[1H02] Research and development of innovative technologies for nuclear reactor core

(2)High temperature steam oxidation and wate corrosion characteristics of silicon carbides for reactor core

＊Yoshihiro Hyodo¹, Yumiko Tsuchiya¹, Fumihisa Kano¹, Sosuke Kondo², Tatsuya Hinoki² (1.Toshiba Corporation , 2.Kyoto University)

10:30 AM - 10:45 AM

[1H03] Research and development of innovative technologies for nuclear core material with enhanced safety

Environmentally-controlled electron irradiation experiment of SiC materials for reactor core

＊Naoyuki Hashimoto¹, Shigehito Isobe¹, Fumihisa Kano², Kazunari Okonogi² (1.Hokkaido University, 2.Toshiba Corporation)

10:45 AM - 11:00 AM

[1H04] Research and development of innovative technologies for nuclear reactor core material with enhanced safety

(4)Irradiation effects on the hydrothermal corrosion of SiC

＊Sosuke Kondo¹, Tatsuya Hinoki¹, Yoshihiro Hyodo², Yumiko Tsuchiya², Fumihisa Kano² (1.IAE, Kyoto University, 2.TOSHIBA Corporation)

11:00 AM - 11:15 AM

[1H05] Research and development of innovative technologies for nuclear reactor core
material with enhanced safety

(5)The joining technology of SiC for nuclear reactor core material

＊Toshiyuki Tazawa¹, Yoshiiro Hyodo¹, Fumihisa Kano¹, Kazunari Okonogi¹, Kazuo Kakiuchi¹ (1.TOSHIBA Corporation)

11:15 AM - 11:30 AM

[1H06] Research and development of innovative technologies for nuclear reactor core material with enhanced safety

(6)Plant feasibility evaluation, transient and safety analysis

＊Fumie Sebe¹, Rei Kimura¹, Yutaka Takeuchi¹, Kazuo Kakiuchi², Kazunari Okonogi² (1.TOSHIBA CORPORATION Power Systems Company, 2.TOSHIBA CORPORATION Power Systems Company IEC)

11:30 AM - 11:45 AM

[1H07] Performance of Solid Electrolyte Oxygen Sensor with Solid Fe/Fe₃O₄ Reference Electrode for Liquid Lead-bismuth Eutectic

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

11:45 AM - 12:00 PM

[1H08] Molecular Dynamics Study of Metallic Impurity Diffusion in Liquid Lead-bismuth Eutectic (LBE)

＊Yun GAO¹, Guido Raos², Carlo Cavallotti², Minoru Takahashi¹ (1.Tokyo Institute of Technology, 2.Politecnico di Milano)

Oral Presentation

[1H09-13] SiC-2

Sat. Mar 26, 2016 2:45 PM - 4:05 PM Room H (Lecture Rooms B B204)

Chair: Akira Hasegawa (Tohoku Univ.)

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2:45 PM - 3:00 PM

[1H09] Current status of SiC/SiC Fuel Cladding/Assembly Research by NITE method (Project SCARLET)

＊HIROTATSU KISHIMOTO¹, Naofumi Nakazato¹, Joon-Soo Park¹, Akira Kohyama¹ (1.Muroran Institute of Technology)

3:00 PM - 3:15 PM

[1H10] Recent Accomplishment of “INSPIRE” Project for R&D of SiC/SiC Fuel Cladding by NITE Method

＊Joon-Soo Park¹, Hirotatsu Kishimoto², Naofumi Nakazato², Akira Kohyama¹ (1.OASIS,MuroranIT, 2.MuroranIT)

3:15 PM - 3:30 PM

[1H11] Corrosion Behavior of NITE-SiC/SiC Fuel Cladding under High Temperature/Pressurized Water

＊Naofumi Nakazato¹, Joon-Soo Park¹, Masato Honma¹, Eri Yanagiya¹, Hirotatsu Kishimoto¹, Masahiro Saitoh², Tatsuo Shikama², Akira Kohyama¹ (1.Muroran Institute of Technology, 2.Hachinohe Institute of Technology)

3:30 PM - 3:45 PM

[1H12] Effect of size and notch shape in the tensile test on NITE-SiC/SiC cladding tube

＊Juhyeon Yu¹, Hirotatsu Kishimoto^2,1, Naofumi Nakazato¹, Joon-Soo Park², Akira Kohyama² (1.Muroran Institute of Technology, 2.OASIS, Muroran Institute of Technology)

3:45 PM - 4:00 PM

[1H13] Radiation damage analysis of high purity SiC by TEM

＊Mohd Idzat Idris¹, Toyohiko Yano¹, Katsumi Yoshida¹ (1.Tokyo Institute of Technology)

Time reserved for Chair （4:00 PM - 4:05 PM）

Oral Presentation

[1H14-21] ODS Structure materials Ni alloys

Sat. Mar 26, 2016 4:05 PM - 6:15 PM Room H (Lecture Rooms B B204)

Chair: Naoyuki Hashimoto (Hokkaido Univ.)

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4:05 PM - 4:20 PM

[1H14] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(1)Evaluation of failure limit correlation under an accident condition

＊Yasuhide Yano¹, Shoich Kato¹, Satoshi Ohtsuka¹, Toshihiko Inoue¹, Takashi Tanno¹, Hiroshi Oka¹, Tomohiro Furukawa¹, Takeji Kaito¹, Shigeharu Ukai², Akihiko Kimura³ (1.JAEA, 2.Hokkaido Univ., 3.Kyoto Univ.)

4:20 PM - 4:35 PM

[1H15] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(2)Analysis of microstructure at high temperature

＊Naoko OONO¹, Ken Nakamura¹, Shigeharu Ukai¹, Takeji Kaito², Tadahiko Torimaru³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1.Hokkaido Univ., 2.JAEA, 3.NFD, 4.Kyoto Univ., 5.Tokyo Tech.)

4:35 PM - 4:50 PM

[1H16] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(3)α/α′ phase decomposition under thermal aging

＊Akihiko Kimura¹, Kiyohiro Yabuuchi¹, Wentuo Han¹, Naoko Oono², Shigeharu Ukai², Takeji Kaito³, Tadahiko Torimaru⁴, Shigenari Hayashi⁵ (1.Kyoto University, 2.Hokkaido University, 3.JAEA, 4.NFD, 5.Institute of Tokyo Technology)

4:50 PM - 5:05 PM

[1H17] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(4)Evaluation of Ion Irradiation Effect

＊Kiyohiro Yabuuchi¹, Wentuo Han¹, Akihiko Kimura¹, Takeji Kaito³, Tadahiko Torimaru⁴, Shigenari Hayashi⁵, Naoko Oono², Shigeharu Ukai² (1.IAE, Kyoto Univ., 2.Hokkaido Univ., 3.JAEA, 4.NFD, 5.Institute of Tokyo Univ.)

5:05 PM - 5:20 PM

[1H19] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(5)Order phase formation due to 8-15 wt.% Al addition in Fe-Cr-Al ferritic steels

＊Bikas Maji¹, Shigeharu Ukai¹, Naoko Oono¹, Takeji Kaito², Tadahiko Torimaru³, Akihiko Kimura⁴, Shigenari Hayashi⁵ (1.Hokkaido University, 2.Japan Atomic Energy Agency, 3.Nippon Nuclear Fuel Development Co., LTD., 4.Kyoto University, 5.Tokyo Institute of Technology)

5:20 PM - 5:35 PM

[1H18] R&D of fuel cladding of ODS ferritic steel for maintaining fuel integrity at accidental high temperature condition (2)

(6)Steam oxidation at severe accident conditions

＊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 )

5:35 PM - 5:50 PM

[1H20] Effects of heating on the strengths and microstructures of reactor structural materials during severe accident

Yuuto Aoki¹, Keita Yoshinaga¹, ＊Shiro Jitsukawa¹ (1.NIT Fukushima College)

5:50 PM - 6:05 PM

[1H21] Grain Boundary Cavity Formation at Crack Tip of PWSCC of Alloy 690

＊Takumi Terachi¹, Tomoki Miyamoto¹, Takuyo Yamada¹, Nobuo Totsuka¹, Koji Arioka¹ (1.Institute of Nuclear Safety System, Incorporated)

Time reserved for Chair （6:05 PM - 6:15 PM）

Oral Presentation

[2H01-07] Zr alloys

Sun. Mar 27, 2016 9:30 AM - 11:15 AM Room H (Lecture Rooms B B204)

Chair: Kazunori Morishita (Kyoto Univ.)

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9:30 AM - 9:45 AM

[2H01] Degradation assessment of hydrogenated zirconium alloy

＊Hiroaki Muta¹, Sho Kano², Huilong Yang³, Zishou Zhao³, Daichi Kunii³, Yasunari Shinohara⁴, Hiroaki Abe² (1.Osaka University, 2.University of Tokyo, 3.Tohoku University, 4.NDC)

9:45 AM - 10:00 AM

[2H02] Microstructure Evolution of Zr-Nb Alloys Subjected to Corrosion in Simulated PWR Primary Water

＊Yoshitaka Matsukawa¹, Shuhei Kitayama¹, Hiroaki Muta², Kenta Murakami³, Yasunari Shinohara⁴, Hiroaki Abe³ (1.Institute for Materials Research, Tohoku University, 2.Osaka University, 3.The University of Tokyo, 4.NDC)

10:00 AM - 10:15 AM

[2H03] Deformation microstructure analysis of Zr-Nb alloy under uniaxial tensile and A-EDC test, and irradiation effect

＊Sho Kano¹, Huilong Yang², Zhao Zishou², Daichi Kunii², Hiroaki Muta³, Kenta Murakami¹, Yasunari Shinohara⁴, Hiroaki Abe¹ (1.The University of Tokyo, 2.Tohoku University, 3.Osaka University, 4.NDC)

10:15 AM - 10:30 AM

[2H04] Behavior of precipitate in oxide film of Zr alloy under Zr ion irradiation

＊Katsuhito Takahashi¹, Tomio Iwasaki¹, Kenta Murakami² (1.Hitachi, Ltd., 2.Tokyo Univ.)

10:30 AM - 10:45 AM

[2H05] Crstal structures of zirconium oxides formed by water corrosion around room temperature

＊Teppei Otsuka¹, Kenichi Hashizume¹, Osamu Kato², Tsuyoshi Tateishi³, Tomofumi Sakuragi⁴, Satoshi Yoshida⁴ (1.Kyushu Univ., 2.Kobe steel, 3.Kobelco, 4.RWMC)

10:45 AM - 11:00 AM

[2H06] Oxidation and hydrogen absorption of Zircaloy-2 in high temperature steam at different partial pressures and oxidation time

＊Takaya Furuta¹, Yuji Hatano¹, Kenji Matsuda¹, Sakamoto Kan² (1.University of Toyama, 2.Nippon Nuclear Fuel Development co., ltd.)

11:00 AM - 11:15 AM

[2H07] Effect of interal pressure on oxidation of Zircaloy-2 cladding tube under steam

＊Ikuo Ioka¹, Hitoshi Kato¹, Hiroaki Ogawa¹, Masahiko Osaka¹ (1.Japan Atomic Energy Agency)

Oral Presentation

[2H08-10] Stainless Steels

Sun. Mar 27, 2016 11:15 AM - 12:00 PM Room H (Lecture Rooms B B204)

Chair: Hiroaki Abe (Univ. of Tokyo)

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11:15 AM - 11:30 AM

[2H08] Tensile fracture behavior at grain boundary in neutron-irradiated stainless steels

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

11:30 AM - 11:45 AM

[2H09] Aging effect on SCC Growth of Cast Austenitic Stainless Steels in High Temperature Water

＊Takuyo Yamada¹, Takumi Terachi¹, Tomoki Miyamoto¹, Koji Arioka¹ (1.Institute of Nuclear Safety System, inc.)

11:45 AM - 12:00 PM

[2H10] A first principle study on the composition deviation of Ni-Si precipitates formed in irradiated stainless steel

＊Dongyue CHEN¹, Kenta MURAKAMI², Naoto SEKIMURA¹ (1.The University of Tokyo, Department of Nuclear Engineering and Management, School of Engineering, 7-3-1 Hongo Bunkyo-ku, Tokyo 113-8656, Japan, 2.The University of Tokyo, Nuclear Professional School, School of Engineering, 2-22 Shirakata-Shirane, Tokai-mura, Ibaraki 319-1188, Japan)

Oral Presentation

[2H11-16] Modeling

Sun. Mar 27, 2016 2:45 PM - 4:25 PM Room H (Lecture Rooms B B204)

Chair: Yoshitaka Matsukawa (Tohoku Univ.)

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2:45 PM - 3:00 PM

[2H11] MD simulations to evaluate the effects of stacking fault energy on the interaction between an edge dislocation and a Frank loop

(1)effects of stacking fault energy on the interaction morphology

＊Taira Okita¹, Yujiro Hayashi², Sho Hayakawa², Mitsuhiro Itakura³ (1.Research into Artifacts, Center for Engineering, the University of Tokyo, 2.Department of Systems Innovation, School of Engineering, the University of Tokyo, 3.Center for Computational Science & e- Systems, Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[2H12] MD simulations to evaluate the effects of stacking fault energy on the interaction between an edge dislocation and a Frank loop

(2)Change in the interaction morphorogy with loop size

＊Yujiro Hayashi¹, Taira Okita², Mitsuhiro Itakura³ (1. Department of systems Innovation, School of engineering, The University of Tokyo, 2.Research into Artifacts, Center for Engineering, the University of Tokyo, 3.Center for Computational Science & e- Systems, Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[2H13] Molecular dynamics simulation to reveal the effect of stacking fault energy on defect cluster formation during collision cascade

＊Yingjuan Yang¹, Junichi Hirabayashi¹, Taira Okita², Mitsuhiro Itakura³ (1. School of Engineering, the University of Tokyo, 2.Research into Artifacts, Center for Engineering, the University of Tokyo, 3.Center for Computational Science & e- Systems, Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[2H14] Conservative climb motion for a cluster of self-interstitial atoms toward an edge dislocation in BCC-Fe

＊Sho Hayakawa¹, Taira Okita², Mitsuhiro Itakura³, Masaatsu Aichi² (1.School of Engineering, the University of Tokyo, 2.Research into Artifacts, Center for Engineering, the University of Tokyo, 3.Center for Computational Science & e-Systems, Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[2H15] Modeling Irradiation Embrittlement of Reactor Pressure Vessel Steel

(1)Monte Carlo Simulation of Defect Cluster Formation

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

4:00 PM - 4:15 PM

[2H16] Modeling Irradiation Embrittlement of Reactor Pressure Vessel Steel

(2)Risk Evaluation for Advanced Inspection of RPV Integrity

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

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

Oral Presentation

[2H17-22] RPV Cladding Tubes

Sun. Mar 27, 2016 4:25 PM - 6:05 PM Room H (Lecture Rooms B B204)

Chair: Taira Okita (Univ. of Tokyo)

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4:25 PM - 4:40 PM

[2H17] Effects of alloying elements on neutron irradiation properties of RPV model steels

＊Tomohiro Kobayashi¹, Kenji Nishida¹, Akiyoshi Nomoto¹, Kenji Dohi¹, Taiki Aizawa², Kenta Nishimoto² (1.Central Research Institute of Electric Power Industry, 2.Japan Steel Works)

4:40 PM - 4:55 PM

[2H18] Evaluation of the relationship between microstructure and hardness in neutron irradiated reactor pressure vessel model alloys following thermal ageing

＊Liang Chen^1,2, Kenji Nishida², Kenta Murakami¹, Kenji Dohi², Li Liu¹, Naoto Sekimura¹ (1.Univ. Tokyo, 2.CRIEPI)

4:55 PM - 5:10 PM

[2H19] Evaluations of mechanical properties and degradations in nuclear fuel cladding tubes

＊Hiroaki ABE¹, Naoto Sekimura¹, Hiroaki Muta², Akira Hasegawa³, Yoshiharu Murase⁴, Yasunari Shinohara⁵ (1.University of Tokyo, 2.Osaka University, 3.Tohoku University, 4.NIMS, 5.NDC)

5:10 PM - 5:25 PM

[2H20] Evaluation of mechanical properties of cladding tube under multi axial stress states

＊Yasunari Shinohara¹, Toshiya Kido¹, Hiroaki Abe² (1.Nuclear Development Corporation, 2.University of Tokyo)

5:25 PM - 5:40 PM

[2H21] Evaluation of mechanical properties in circumferential direction of tubular materials (Development of advanced expansion due to compression test)

＊Daichi Kunii¹, Kenji Nishimura¹, Zishou Zhao¹, Shiori Kishita¹, Tomonori Abe¹, Sho Kano², Yoshitaka Matsukawa¹, Yuhki Satoh¹, Hiroaki Abe² (1.Tohoku University, 2.The University of Tokyo)

5:40 PM - 5:55 PM

[2H22] Development of short-tube test technique using expansion due to compressed liquid(EDC-L)

＊Masafumi Nakatsuka¹, Kan Sakamoto² (1.Zirco-technology, 2.NFD)

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

Sessions

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

[1H01-08] Pb-Bi/SiC-1

(1)Development and evaluation of SiC material for nuclear reactor core application

(2)High temperature steam oxidation and wate corrosion characteristics of silicon carbides for reactor core

Environmentally-controlled electron irradiation experiment of SiC materials for reactor core

(4)Irradiation effects on the hydrothermal corrosion of SiC

(5)The joining technology of SiC for nuclear reactor core material

(6)Plant feasibility evaluation, transient and safety analysis

[1H09-13] SiC-2

[1H14-21] ODS Structure materials Ni alloys

(1)Evaluation of failure limit correlation under an accident condition

(2)Analysis of microstructure at high temperature

(3)α/α′ phase decomposition under thermal aging

(4)Evaluation of Ion Irradiation Effect

(5)Order phase formation due to 8-15 wt.% Al addition in Fe-Cr-Al ferritic steels

(6)Steam oxidation at severe accident conditions

[2H01-07] Zr alloys

[2H08-10] Stainless Steels

[2H11-16] Modeling

(1)effects of stacking fault energy on the interaction morphology

(2)Change in the interaction morphorogy with loop size

(1)Monte Carlo Simulation of Defect Cluster Formation

(2)Risk Evaluation for Advanced Inspection of RPV Integrity

[2H17-22] RPV Cladding Tubes

Authentication

(1)Development and evaluation of SiC material for nuclear reactor core applica
tion