Oral Presentation

[1L01-03] Tritium permeation

Sat. Mar 26, 2016 2:45 PM - 3:35 PM Room L (Lecture Rooms C C105)

Chair: Yuji Hatano (Univ. of Toyama)

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2:45 PM - 3:00 PM

[1L01] Deuterium migration behavior in ceramics-metal multilayer coatings

＊Seira Horikoshi¹, Jumpei Mochizuki¹, Cui Hu¹, Yasuhisa Oya¹, Takumi Chikada¹ (1.Fuculty of Science, Shizuoka University)

3:00 PM - 3:15 PM

[1L02] Deuterium permeation behavior in erbium oxide coatings irradiated by iron ion at elevated temperature

＊Takumi Chikada¹, Seira Horikoshi¹, Jumpei Mochizuki¹, Cui Hu¹, Freimut Koch², Kiyohiro Yabuuchi³, Yasuhisa Oya¹ (1.Shizuoka University, 2.Max-Planck-Institut für Plasmaphysik, 3.Kyoto University)

3:15 PM - 3:30 PM

[1L03] Fabrication and deuterium permeation measurements of yttrium oxide coating containing carbide nanoparticles.

＊Jumpei Mochizuki¹, Seira Horikoshi¹, Cui Hu¹, Yasuhisa Oya¹, Takumi Chikada¹ (1.Faculty of Science, Shizuoka University)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral Presentation

[2L07-11] Fusion materials engineering (Divertor)

Sun. Mar 27, 2016 2:45 PM - 4:05 PM Room L (Lecture Rooms C C105)

Chair: Bun Tsuchiya (Meijo Univ.)

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2:45 PM - 3:00 PM

[2L07] Application of Friction-Stir Process for Mechanically Strengthening CuCrZr-alloy

＊Dai Hamaguchi¹, Yoshiaki Morisada², Hidetoshi Fujii², Hiroyasu Tanigawa¹, Kazumi Ozawa¹ (1.Japan Atomic Energy Agency, 2.Osaka University)

3:00 PM - 3:15 PM

[2L08] Hydrogen isotope exchange in tungsten damaged by self-ion irradiation

＊Yoshihiro Susuki¹, Ikuji Takagi¹ (1.Kyoto University)

3:15 PM - 3:30 PM

[2L09] KMC simulation of rhenium and osmium interstitial atoms in tugnsten

＊Tomoaki Suzudo¹, Akira Hasegawa² (1.JAEA, 2.Tohoku Univ.)

3:30 PM - 3:45 PM

[2L10] Grain structure and tensile property changes of rhenium and potassium doped tungsten materials due to recrystallization

＊Makoto Fukuda¹, Kohei Tsuchida¹, Yuma Kajishima¹, Akira Hasegawa¹, Shuhei Nogami¹ (1.Tohoku university)

3:45 PM - 4:00 PM

[2L11] Deformation behavior of tungsten materials for plasma facing components at high temperature

＊Akira Hasegawa¹, Yasuyuki Sakai¹, Tsunenori Tabata¹, Makoto Fukuda¹, Shuhei Nogami¹ (1.Tohoku university)

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

Oral Presentation

[2L12-16] Fusion materials engineering (Tungsten materials)

Sun. Mar 27, 2016 4:05 PM - 5:25 PM Room L (Lecture Rooms C C105)

Chair: Dai Hamaguchi (JAEA)

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4:05 PM - 4:20 PM

[2L12] Structual Integrity Evaluation of Divertor after Cyclic Heat Loading

＊Michitoshi Toyota¹, Atsuo Sakata¹, Wenhai Guan¹, shuhei Nogami¹, Makoto Fukuda¹, Akira Hasegawa¹ (1.Tohoku University)

4:20 PM - 4:35 PM

[2L13] Behavior of Tungsten with Heavy Ion Irradiation

(1)Hardening Behavior in Heavy Ion Irradiation on Rhenium Doped Tungsten

＊Tsunenori Tabata¹, Taehyun Hwang¹, Makoto Fukuda¹, Akira Hasegawa¹, Shuhei Nogami ¹, Hiroyasu Tanigawa², Kazumi Ozawa² (1.Department of Quantum Science and Energy Engineering, Tohoku University, 2.Japan Atomic Energy Agency)

4:35 PM - 4:50 PM

[2L14] Behavior of Tungsten with Heavy Ion Irradiation

(2)Multiple effect of Re and K addition on irradiation effect of W

＊TAEHYUN HWANG¹, Ohno Satoshi¹, Tsunenori Tabata¹, Makoto Fukuda¹, Shuhei Nogami¹, Akira Hasegawa¹, Kazumi Ozawa², Hiroyasu Tanigawa² (1.Tohoku university, 2.Japan Atomic Energy Agency)

4:50 PM - 5:05 PM

[2L15] Variation of Structural Strength of Tungsten Divertor by Microstructure Control and Alloying

＊WENHAI GUAN¹, Shuhei Nogami¹, Makoto Fukuda¹, Michitoshi Toyota¹, Kento Niki¹, Akira Hasegawa¹ (1.Tohoku University)

5:05 PM - 5:20 PM

[2L16] Surface morphology and deuterium retention on tungsten surface melted by high heat flux

＊yukinori hamaji¹, Lee Heun², Arkadi Kreter³, Soeren Moeller¹, Masayuki Tokitani¹, Suguru Masuzaki¹, akio Sagara¹, Makoto Oya², Yoshio Ueda², Ryuichi Sakamoto¹ (1.National institute for Fusion Science, 2.Osaka University, 3.Forschungszentrum Juelich GmbH)

Time reserved for Chair （5:20 PM - 5:25 PM）

Oral Presentation

[2L17-20] Fusion reactor materials (Material strength evaluation method / Structual health monitoring)

Sun. Mar 27, 2016 5:25 PM - 6:30 PM Room L (Lecture Rooms C C105)

Chair: Ryuta Kasada (Kyoto Univ.)

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5:25 PM - 5:40 PM

[2L17] Diagnostics of surface modification of plasma facing materials using optical spectral reflectance measurements

＊Norihito Tanaka¹, Mitutaka Miyamoto¹, Naoaki Yoshida², Masayuki Tokitani³, Akio Sagara³ (1.Shimane Univ., 2.RIAM, Kyusyu Univ., 3.NIFS)

5:40 PM - 5:55 PM

[2L18] Strength and pressure integrity evaluation of blanket first wall and necessary material data

＊Hisashi Tanigawa¹, Hyoseong Gwon¹, Takanori Hirose¹, Yoshinori Kawamura¹ (1.JAEA)

5:55 PM - 6:10 PM

[2L19] Effect of fabric architecture on hoop strength of SiC/SiC composite tube

＊Takashi Nozawa¹, Ju-hyeon Yu², Joon-soo Park², Hiroyasu Tanigawa¹ (1.JAEA, 2.Muroran Institute of Technology)

6:10 PM - 6:25 PM

[2L20] Development of Fatigue Test Technology for Life Evaluation of Fusion Reactor Materials

＊Shuhei Nogami¹, Wenhai Guan¹, Makoto Fukuda¹, Chiaki Hisaka², Taejoon Kim², Yojiro Akizuki², Fumio Minamiyama², Masaharu Fujiwara², Akira Hasegawa¹ (1.Department of Quantum Science and Energy Engineering, Tohoku University, 2.Kobe Material Testing Laboratory Group)

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

Oral Presentation

[3L01-04] Tritium breeders and neutron multiplier (Fabrication technology and chemical characteristics)

Mon. Mar 28, 2016 9:50 AM - 10:55 AM Room L (Lecture Rooms C C105)

Chair: Takumi Chikada (Shizuoka Univ.)

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9:50 AM - 10:05 AM

[3L01] Status of R&D of advanced neutron multiplier in ITER-BA activity

(20)Granulation and characteristics of Be-Zr beryllides pebbles

Jae-Hwan Kim¹, ＊Tsuyoshi Hoshino¹, Suguru Nakano ¹, Yoshiaki Akatsu¹, Masaru Nakamichi ¹ (1.Japan Atomic Energy Agency)

10:05 AM - 10:20 AM

[3L02] Pebble Fabrication of Novel Advanced Tritium Breeders Using a Solid Solution of Li_2+xTiO_3+y with Li₂ZrO₃

＊Tsuyoshi Hoshino¹ (1.Japan Atomic Energy Agency)

10:20 AM - 10:35 AM

[3L03] Study on quantity fabrication and purity control of lithium-lead as fusion liquid breeder

＊CHANGHO PARK¹, MASATOSHI KONDO², TAKASHI NOZAWA¹, HIROYASU TANIGAWA¹ (1.Japan Atomic Energy Agency, 2.Tokyo Institute of Technology)

10:35 AM - 10:50 AM

[3L04] Experimental study on compatibility of reduced activation ferritic martensitic steel with flowing Pb-17Li

Metallurgical analysis of corrosion-erosion part of steel surface and discussion on corrosion-erosion mechanism

＊Masatoshi Kondo¹, Yoshimitsu Hishinuma², Takeo Muroga² (1.Tokyo Institute of Technology, Research Laboratory for Nuclear Reactors, 2.National Institute for Fusion Science, Department of Helical Plasma Research )

Time reserved for Chair （10:50 AM - 10:55 AM）

Oral Presentation

[3L05-08] Tritium breeders and neutron multiplier (adsorption and desorption of hydrogen isotopes / chemical stability)

Mon. Mar 28, 2016 10:55 AM - 12:00 PM Room L (Lecture Rooms C C105)

Chair: Teruya Tanaka (NIFS)

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10:55 AM - 11:10 AM

[3L05] Evaluation of atomic composition and deuterium desorption behavior of Li₂TiO₃ after hydrogen gas exposure at elevated temperatures

＊Yuta Suzuki¹, Yuji Nobuta¹, Yuji Yamauchi¹, Tsuyoshi Hoshino² (1.Hokkaido Univ. Graduate School of Engineering, 2.JAEA)

11:10 AM - 11:25 AM

[3L06] CO₂ absorption characteristics of a blanket candidate material Li₂TiO₃ under various atmospheric exposures

＊hodaka nakamura¹, Tsubasa Takeda¹, Ryo Hirayama¹, Sho Nagai¹, Akira Taniike¹, Yuichi Furuyama¹ (1.kobe university)

11:25 AM - 11:40 AM

[3L07] Hydrogen retention behavior in beryllide as advanced neutron multipliers

＊Yuta Fujii¹, Mitsutaka Miyamoto¹, Jae-Hwan Kim², Masaru Nakamichi², Hirotomo Iwakiri³ (1.Shimane Univ., 2.JAEA, 3.Univ. of the Ryukyus)

11:40 AM - 11:55 AM

[3L08] Dissolution of lithium compounds in ethanol

＊yasushi hirakawa¹, tomohiro furukawa¹ (1.Japan Atomic Energy Agency)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral Presentation

[3L09-15] Material Engineering for Fusion Reactor (Low Activation Structural Material)

Mon. Mar 28, 2016 2:45 PM - 4:30 PM Room L (Lecture Rooms C C105)

Chair: Takeo Nishitani (NIFS)

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2:45 PM - 3:00 PM

[3L09] Effect of grain boundaries on microstructural evolution in Ferritic/martensitic steels under irradiation

＊Chisei Morimoto¹, Naoyuki Hashimoto¹, Dai Hamaguchi², Hiroyasu Tanigawa², Yoshiyuki Watanabe² (1.Graduate School of Engineering Hokkaido Univ. , 2.JAEA)

3:00 PM - 3:15 PM

[3L10] He Retention of He⁺ Ion-irradiated Pyrochlore-type Oxides

＊Bun Tsuchiya¹, Takuya YAMAMOTO², Kazuhito OHSAWA³, George ODETTE² (1.Faculty of Science and Technology, Meijo University, 2.Department of Chemical Engineering, University of California Santa Barbara, 3.Institute for Applied Mechanics, Kyushu University)

3:15 PM - 3:30 PM

[3L11] Development of low-activation vanadium alloy for recycling within 10 years after use in fusion reactors

(1)Fabrication of highly-purified vanadium metal and its alloys

＊TAKUYA NAGASAKA¹, Teruya Tanaka¹, Takuya Goto¹, Akio Sagara¹, Kazuhiro Nomura², Seiji Sakurai², Hideo Yoshinaga², Yuki Satoh³, Takamasa Sugawara³, Kunio Yubuta³ (1.National Institute for Fusion Science, 2.Taiyo Koko Co. Ltd., 3.Institute for Materials Research, Tohoku University)

3:30 PM - 3:45 PM

[3L12] Tensile properties for ion-irradiated F82H steel by micro-tensile testing

＊Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹, Masami Ando², Hiroyasu Tanigawa² (1.Institute of Nuclear Safety System, 2.Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[3L13] Tensile fracture behavior of high dose irradiated reduced activation ferritic/martensitic steel F82H

＊Hiroyasu Tanigawa¹, Hideo Sakasegawa¹, Takanori Hirose¹, Yutai Katoh² (1.Japan Atomic Energy Agency, 2.Oak Ridge National Laboratory)

4:00 PM - 4:15 PM

[3L14] Preliminary design fatigue curves for reduced activation ferritic/martensitic steel, F82H

＊Takanori Hirose¹, Hideo Sakasegawa¹, Hisashi Tanigawa¹, Hiroyasu Tanigawa¹, Yoshinori Kawamura¹ (1.JAEA)

4:15 PM - 4:30 PM

[3L15] Void Swelling Behavior of Multi-Ion Irradiated F82H

＊Masami Ando¹, Hiroyasu Tanigawa¹, Hironori Kurotaki¹ (1.Japan Atomic Energy Agency)

Sessions

V. Fusion Energy Engineering » 501-2. Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1L01-03] Tritium permeation

[2L07-11] Fusion materials engineering (Divertor)

[2L12-16] Fusion materials engineering (Tungsten materials)

(1)Hardening Behavior in Heavy Ion Irradiation on Rhenium Doped Tungsten

(2)Multiple effect of Re and K addition on irradiation effect of W

[2L17-20] Fusion reactor materials (Material strength evaluation method / Structual health monitoring)

[3L01-04] Tritium breeders and neutron multiplier (Fabrication technology and chemical characteristics)

(20)Granulation and characteristics of Be-Zr beryllides pebbles

Metallurgical analysis of corrosion-erosion part of steel surface and discussion on corrosion-erosion mechanism

[3L05-08] Tritium breeders and neutron multiplier (adsorption and desorption of hydrogen isotopes / chemical stability)

[3L09-15] Material Engineering for Fusion Reactor (Low Activation Structural Material)

(1)Fabrication of highly-purified vanadium metal and its alloys

Authentication