Oral presentation

[1A01-06] Liquid Metal and Functional Materials

Mon. Mar 13, 2023 10:15 AM - 11:55 AM Room A (11 Bildg.1F 1101)

Chair:Teppei Otsuka(Kindai Univ.)

10:15 AM - 10:30 AM

[1A01] Formation behavior and adhesion strength of protective oxide layer on FeCrAl-ODS alloys

*Yoshiki Kitamura¹, Naoko Oono², Yoshimitsu Hishinuma³, Masatoshi Kondo¹ (1. Tokyo Tech, 2. Yokohama Natl. Univ., 3. NIFS)

10:30 AM - 10:45 AM

[1A02] Investigation on repair technique of functional coatings by recoating

*Tetsuma Ito¹, Hikaru Fujiwara¹, Kento Shirota¹, Wataru Matsuura¹, Kheim Do Duy¹, Yuka Shimizu¹ (1. Shizuoka University )

10:45 AM - 11:00 AM

[1A03] Fabrication and characterization of silica-based functional coating

*Yuka Shimizu¹, Hikaru Fujiwara¹, Kento Shirota¹, Wataru Matsuura¹, Tetsuma Ito¹, Takumi Chikada¹ (1. Shizuoka Univ.)

11:00 AM - 11:15 AM

[1A04] α-Al₂O₃layer formation on inner surface of APMT tube for reduction of MHD pressure drop in liquid metal blanket manifold system

*Ryuhei Muto¹, Ryunosuke Nishio¹, Teruya Tanaka², Masatoshi Kondo¹ (1. Tokyo Tech, 2. NIFS)

11:15 AM - 11:30 AM

[1A05] Reduction of MHD pressure drop by electrical insulating α-Al₂O₃ layer on FeCrAl-ODS alloys in liquid breeder blankets of fusion reactors

*Ryunosuke Nishio¹, Teruya Tanaka², Naoko Oono³, Masatoshi Kondo¹ (1. Tokyo Tech, 2. NIFS, 3. Yokohama Natl. Univ. )

11:30 AM - 11:45 AM

[1A06] Lithium isotope distribution between liquid metal and ternary chloride molten salt

*Ryo Ito¹, Fu Nomoto¹, Shun Aratani¹, Keisuke Mukai¹, Juro Yagi¹ (1. Kyoto Univ.)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[1A07-11] Divertor and Superconducting Materials

Mon. Mar 13, 2023 2:45 PM - 4:10 PM Room A (11 Bildg.1F 1101)

Chair:satoshi konishi(Kyoto Fusioneering)

2:45 PM - 3:00 PM

[1A07] High Accurate Evaluation of Deuterium and Helium Behavior in Tungsten by STEM-EELS

*Kohei Sano¹, Tomoya Sawae¹, Mitsutaka Haruta², Hiroki Kurata², Mitsutaka Miyamoto¹ (1. Shimane Univ., 2. Kyoto Univ.)

3:00 PM - 3:15 PM

[1A08] Effects of Mo or Zr Addition on Plasma Irradiation Resistance of W-Y₂O₃ Alloy

*Qiu Xu¹, Mitsutaka Miyamoto², Masayuki Tokitani³, Koichi Sato⁴ (1. Institute for Integrated Radiation and Nuclear Science, Kyoto University, 2. Shimane University, 3. National Institute for Fusion Science, 4. Kagoshima University)

3:15 PM - 3:30 PM

[1A09] Strain reduction in tungsten due to annealing and change in hydrogen isotope permeation behavior.

*Hiroki Yata¹, Kobayashi Makoto^1,2, Takuya Nagasaka^1,2 (1. The Graduate University for Advanced Studies, 2. National Institute for Fusion Science)

3:30 PM - 3:45 PM

[1A10] Role of nuclear transmuted Re on tungsten by HD mixed plasma irradiation Hydrogen isotope permeation behavior for W-Re alloy by HD mixed plasma exposure

*Yuzuka Hoshino¹, Naoko Ashikawa², Yasuhisa Oya¹ (1. Shizuoka Univ., 2. NIFS)

3:45 PM - 4:00 PM

[1A11] Evaluation of irradiation defects in REBCO with first-principal calculation

*Kota Sakurai¹, Naoko Oono¹ (1. Yokohama Natl. Univ.)

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

Oral presentation

[1A12-15] Neutron Multiplier and Solid Breeder Materials

Mon. Mar 13, 2023 4:10 PM - 5:15 PM Room A (11 Bildg.1F 1101)

Chair:Qiu Xu(Kyoto Univ.)

4:10 PM - 4:25 PM

[1A12] In-situ observation of gas retention behavior in Be using TEM equipped with a mass spectrometer

*Tomoya Nakao¹, Tomoya Sawae¹, Shinsuke Okubo¹, Mitsutaka Miyamoto¹ (1. Shimane Univ.)

4:25 PM - 4:40 PM

[1A13] Changes in Tritium Release Behavior of Li₂TiO₃-Li₄SiO₄ Mixed Ceramic Materials by Lead Addition Rate

*Asahi Sanfukuji¹, Qilai Zhou², Tan Guangfan³, Makoto Koayashi⁴, Yasuhisa Oya¹ (1. Shizuoka Univ., 2. Wuhan University of Technology, 3. University of Science and Technology Beijing, 4. NIFS)

4:40 PM - 4:55 PM

[1A14] Effect of irradiation dose on tritium release behavior of neutron irradiated Li₂TiO₃-Li₄SiO₄ mixed ceramic

*Qilai Zhou^1,2, Asahi Sanfukuji¹, Tan Guangfan^1,3, Oya Yasuhisa¹ (1. Shizuoka Univ., 2. Wuhan Univ. of Technol., 3. The Univ. of Sci. and Technol. Beijing)

4:55 PM - 5:10 PM

[1A15] Comparison of tritium recovery behavior in Li2TiO3-Li4SiO4 ceramic pebbles and powder irradiated with neutron

*Guangfan Tan¹, sanfukuji asahi², hirata shiori², Qilai Zhou³, Yasuhisa Oya², Yingchun Zhang¹ (1. University of Science and Technology Beijing., 2. Shizuoka Univ., 3. Wuhan University of Technology.)

Time reserved for Chair （5:10 PM - 5:15 PM）

Sessions

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[1A01-06] Liquid Metal and Functional Materials

[1A01] Formation behavior and adhesion strength of protective oxide layer on FeCrAl-ODS alloys

[1A02] Investigation on repair technique of functional coatings by recoating

[1A03] Fabrication and characterization of silica-based functional coating

[1A04] α-Al₂O₃layer formation on inner surface of APMT tube for reduction of MHD pressure drop in liquid metal blanket manifold system

[1A05] Reduction of MHD pressure drop by electrical insulating α-Al₂O₃ layer on FeCrAl-ODS alloys in liquid breeder blankets of fusion reactors

[1A06] Lithium isotope distribution between liquid metal and ternary chloride molten salt

[1A07-11] Divertor and Superconducting Materials

[1A07] High Accurate Evaluation of Deuterium and Helium Behavior in Tungsten by STEM-EELS

[1A08] Effects of Mo or Zr Addition on Plasma Irradiation Resistance of W-Y₂O₃ Alloy

[1A09] Strain reduction in tungsten due to annealing and change in hydrogen isotope permeation behavior.

[1A10] Role of nuclear transmuted Re on tungsten by HD mixed plasma irradiation Hydrogen isotope permeation behavior for W-Re alloy by HD mixed plasma exposure

[1A11] Evaluation of irradiation defects in REBCO with first-principal calculation

[1A12-15] Neutron Multiplier and Solid Breeder Materials

[1A12] In-situ observation of gas retention behavior in Be using TEM equipped with a mass spectrometer

[1A13] Changes in Tritium Release Behavior of Li₂TiO₃-Li₄SiO₄ Mixed Ceramic Materials by Lead Addition Rate

[1A14] Effect of irradiation dose on tritium release behavior of neutron irradiated Li₂TiO₃-Li₄SiO₄ mixed ceramic

[1A15] Comparison of tritium recovery behavior in Li2TiO3-Li4SiO4 ceramic pebbles and powder irradiated with neutron

Authentication