Oral presentation

[1M01-05] Ceramics

Mon. Mar 16, 2020 10:30 AM - 11:55 AM Room M (Lecture Bildg. S 3F S-31)

Chair:Katsuhiko Fujii(INSS)

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10:30 AM - 10:45 AM

[1M01] Effect of Tungsten Matrix on Mechanical Properties of SiC Fiber Reinforced W Composites

*YINA DU¹, Bo Huang¹, Tatsuya Hinoki¹, Fujio Shinoda¹, Kanjiro Kawasaki¹ (1. Institute of Advanced Energy,Kyoto Universitiy)

10:45 AM - 11:00 AM

[1M02] Microstructural Response of C/BN Particle Dispersed SiC Materials to Ion Irradiation

*Bo Huang¹, Yina Du¹, Junyeab Lee¹, Kanjiro Kawasaki¹, Fujio Shinoda¹, Tatsuya Hinoki¹ (1. Kyoto Univ.)

11:00 AM - 11:15 AM

[1M03] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(1)Neutron and Helium Implantation Test for B₄C-based Ceramics

*Ryosuke S. S. Maki¹, Fajar Muhammad¹, Jelena Maletaskic¹, Anna Gubarevich¹, Tatsuya Katabuchi¹, Toyohiko Yano¹, Katsumi Yoshida¹, Tohru S. Suzuki², Tetsuo Uchikoshi² (1. Tokyo Tech, 2. NIMS)

11:15 AM - 11:30 AM

[1M04] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(2)Fabrication and Evaluation of Highly Controlled Microstructure in B₄C Neutron Absorber by Magnetic Field-Assisted Colloidal Processing

*Shota Azuma¹, Testuo Uchikoshi¹, Katsumi Yoshida², Tohru S Suzuki¹ (1. NIMS, 2. Tokyo Tech)

11:30 AM - 11:45 AM

[1M05] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(3)Post-Irradiation Microstructure Evaluation of "Joyo" Irradiated B₄C Control Materials

*Yuta Shizukawa¹, Yoshihiro Sekio¹, Toshihiko Inoue¹, Koji Maeda¹, Katsumi Yoshida² (1. JAEA, 2. Tokyo Tech)

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

Oral presentation

[1M06-09] Irradiation Effect 1

Mon. Mar 16, 2020 2:45 PM - 3:50 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Hiroaki Abe(Univ. of Tokyo)

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2:45 PM - 3:00 PM

[1M06] Effects of Ni-Si clusters on loop growth and stability investigated by additional in-situ irradiation

*Dongyue Chen¹, Kenta Murakami², Liang Chen¹, Hiroaki Abe¹, Naoto Sekimura¹ (1. Univ. of Tokyo, 2. Nagaoka Univ. of Tech.)

3:00 PM - 3:15 PM

[1M07] Statistical Arguments on Athermal Defect Production in a-Fe due to Displacement Cascades: Molecular Dynamics Simulation Study

*Yuting Chen¹, Xiaoyong Ruan¹, Toshiki Nakasuji¹, Kazunori Morishita¹, Yoshiyuki Watanabe² (1. KYOTO UNIVERSITY, 2. QST)

3:15 PM - 3:30 PM

[1M08] Evaluation of mechanical properties of steels by using micro-sized tensile specimen

*Shotaro Watanabe¹, Shuhei Nogami¹, Masami Ando², Akira Hasegawa¹ (1. Tohoku Univ., 2. QST)

3:30 PM - 3:45 PM

[1M09] Evaluation of mechanical properties of stainless steel weld by micro-tensile testing

(1)Investigation of size effect

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

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[1M10-12] Iradiation Effect 2

Mon. Mar 16, 2020 3:50 PM - 4:40 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Takeshi Toyama(Tohoku Univ.)

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3:50 PM - 4:05 PM

[1M10] Effects of solute atom clusters on hardening in neutron-irradiated stainless steels

*Katsuhiko Fijii¹, Koji Fukuya¹ (1. INSS)

4:05 PM - 4:20 PM

[1M11] Displacement damage calculation for nuclear reactor materials under ion irradiation with new defect re-combination correction model

*Yosuke Iwamoto¹ (1. JAEA)

4:20 PM - 4:35 PM

[1M12] Visualization and quantification of cascade damage in iron-based alloys

*Kenta Murakami¹, Dongyue Chen², Liang Chen², Hiroaki Abe², Naoto Sekimura², Masahide Suzuki¹ (1. Nagaoka Univ. Tech., 2. Univ. Tokyo)

Time reserved for Chair （4:35 PM - 4:40 PM）

Oral presentation

[2M01-03] Corrosion

Tue. Mar 17, 2020 10:00 AM - 10:50 AM Room M (Lecture Bildg. S 3F S-31)

Chair:Tatsuya Hinoki(Kyoto Univ.)

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10:00 AM - 10:15 AM

[2M01] SCC Mechanistic Study on PWR Structural Materials

Influence of Ni Concentration and Temperature on Corrosion

*Takumi Terachi¹, Takuyo Yamada¹, Makie Okamoto², Tomoki Miyamoto², Koji Arioka¹ (1. INSS, 2. Kobe Material Testing Laboratory Group)

10:15 AM - 10:30 AM

[2M02] Influence of Water Chemistry and Test Temperature on SCC Growth Behavior of Welds and Cast Stainless Steels in Oxygenated High-Temperature Water

*Takuyo Yamada¹, Takumi Terachi¹, Makie Okamoto², Koji Arioka¹ (1. INSS, 2. Kobe Material Testing Laboratory Group)

10:30 AM - 10:45 AM

[2M03] Corrosion of Ni-based alloy with molten fluoride salt under strong oxidizing condition

*Koji Ogasawara¹, Yuma Sekiguchi¹, Takayuki Terai¹ (1. Univ. of Tokyo)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral presentation

[2M04-07] Zirconium

Tue. Mar 17, 2020 10:50 AM - 12:00 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Hideo Watanabe(Kyushu Univ.)

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10:50 AM - 11:05 AM

[2M04] Evaluation of crystal orientation in fracture surface of Zr hydride

*hideaki sanenobu¹, Yuji Ohishi¹, Hiroaki Muta¹ (1. Osaka univ.)

11:05 AM - 11:20 AM

[2M05] Diffusion of oxygen and hydrogen in zirconium alloy oxide films

*Takuto Sakamoto¹, Kana Yamaguchi¹, Ikuji Takagi¹, Katsuhito Takahashi², Kan Sakamoto² (1. Kyoto Univ., 2. NFD)

11:20 AM - 11:35 AM

[2M06] Fuel cladding deformation behavior during anticipated loss of coolant accident at spent fuel pool

(1)As-received Zircaloy-4 cladding tube

*Kinya Nakamura¹, Kenta Inagaki¹, Takeshi Sonoda¹, Satoshi Nishimura¹ (1. CRIEPI)

11:35 AM - 11:50 AM

[2M07] The bending strength of the pre-hydrided cladding tube experienced simulated-LOCA test

*Yuji Okada¹, Masaki Amaya¹ (1. JAEA)

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

Oral presentation

[2M08-12] Reactor Pressure Vessel

Tue. Mar 17, 2020 2:45 PM - 4:10 PM Room M (Lecture Bildg. S 3F S-31)

Chair:Kazunori Morishita(Kyoto Univ.)

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2:45 PM - 3:00 PM

[2M08] In-situ transmission electron microscopy study of evolution of dislocation loops in irradiated reactor pressure vessel model alloys

*Liang Chen¹, Kenta Murakami², Dongyue Chen¹, Hiroaki Abe¹, Zhengcao Li³, Naoto Sekimura¹ (1. Univ. of Tokyo, 2. Nagaoka Univ. of Tech., 3. Tsinghua Univ.)

3:00 PM - 3:15 PM

[2M09] Microstructure analysis of ion-irradiated reactor pressure vessel steel using X-ray absorption

*Keiko Iwata¹, Yoosung Ha¹, Hisashi Takamizawa¹, Masaki Shimodaira ¹, Mitsunori Honda¹, Yoshihiro Okamoto¹ (1. JAEA)

3:15 PM - 3:30 PM

[2M10] In-situ WB-STEM study of annealing process of neutron irradiation induced dislocation loops.

*Kenta Yoshida¹, Yufeng Du¹, Yusuke Shimada¹, Tomoaki Suzudo², Kazuto Arakawa³, Takeshi Toyoma¹, Koji Inoue¹, Somei Ohnuki⁴, Yasuyoshi Nagai¹ (1. Tohoku Univ., 2. JAEA, 3. Shimane Univ., 4. USTB)

3:30 PM - 3:45 PM

[2M11] Uncertainty evaluation of Charpy ductile-to-brittle transition temperature for neutron-irradiated reactor pressure vessel steels

*Hisashi Takamizawa¹, Yutaka Nishiyama¹ (1. JAEA)

3:45 PM - 4:00 PM

[2M12] Effects of irradaition and thermal aging on PRV mock up material of Hamaoka-1(2)

*Hideo Watanabe¹, Tomoki Ohnori², Yasuhiro Kamada³, Hideki Yuya⁴ (1. RIAM, Kyushu Univ.,, 2. Kyushu Univ.,, 3. Iwate Univ.,, 4. Chubu Electric Power C0. Inc.,)

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

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1M01-05] Ceramics

[1M01] Effect of Tungsten Matrix on Mechanical Properties of SiC Fiber Reinforced W Composites

[1M02] Microstructural Response of C/BN Particle Dispersed SiC Materials to Ion Irradiation

[1M03] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(1)Neutron and Helium Implantation Test for B₄C-based Ceramics

[1M04] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(2)Fabrication and Evaluation of Highly Controlled Microstructure in B₄C Neutron Absorber by Magnetic Field-Assisted Colloidal Processing

[1M05] Development of Highly Microstructure-Controlled Ceramic Neutron Absorbers for Improving Safety of Fast Reactors

(3)Post-Irradiation Microstructure Evaluation of "Joyo" Irradiated B₄C Control Materials

[1M06-09] Irradiation Effect 1

[1M06] Effects of Ni-Si clusters on loop growth and stability investigated by additional in-situ irradiation

[1M07] Statistical Arguments on Athermal Defect Production in a-Fe due to Displacement Cascades: Molecular Dynamics Simulation Study

[1M08] Evaluation of mechanical properties of steels by using micro-sized tensile specimen

[1M09] Evaluation of mechanical properties of stainless steel weld by micro-tensile testing

(1)Investigation of size effect

[1M10-12] Iradiation Effect 2

[1M10] Effects of solute atom clusters on hardening in neutron-irradiated stainless steels

[1M11] Displacement damage calculation for nuclear reactor materials under ion irradiation with new defect re-combination correction model

[1M12] Visualization and quantification of cascade damage in iron-based alloys

[2M01-03] Corrosion

[2M01] SCC Mechanistic Study on PWR Structural Materials

Influence of Ni Concentration and Temperature on Corrosion

[2M02] Influence of Water Chemistry and Test Temperature on SCC Growth Behavior of Welds and Cast Stainless Steels in Oxygenated High-Temperature Water

[2M03] Corrosion of Ni-based alloy with molten fluoride salt under strong oxidizing condition

[2M04-07] Zirconium

[2M04] Evaluation of crystal orientation in fracture surface of Zr hydride

[2M05] Diffusion of oxygen and hydrogen in zirconium alloy oxide films

[2M06] Fuel cladding deformation behavior during anticipated loss of coolant accident at spent fuel pool

(1)As-received Zircaloy-4 cladding tube

[2M07] The bending strength of the pre-hydrided cladding tube experienced simulated-LOCA test

[2M08-12] Reactor Pressure Vessel

[2M08] In-situ transmission electron microscopy study of evolution of dislocation loops in irradiated reactor pressure vessel model alloys

[2M09] Microstructure analysis of ion-irradiated reactor pressure vessel steel using X-ray absorption

[2M10] In-situ WB-STEM study of annealing process of neutron irradiation induced dislocation loops.

[2M11] Uncertainty evaluation of Charpy ductile-to-brittle transition temperature for neutron-irradiated reactor pressure vessel steels

[2M12] Effects of irradaition and thermal aging on PRV mock up material of Hamaoka-1(2)

Authentication

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[1M01-05] Ceramics

(1)Neutron and Helium Implantation Test for B4C-based Ceramics

(2)Fabrication and Evaluation of Highly Controlled Microstructure in B4C Neutron Absorber by Magnetic Field-Assisted Colloidal Processing

(3)Post-Irradiation Microstructure Evaluation of "Joyo" Irradiated B4C Control Materials

[1M06-09] Irradiation Effect 1

(1)Investigation of size effect

[1M10-12] Iradiation Effect 2

[2M01-03] Corrosion

Influence of Ni Concentration and Temperature on Corrosion

[2M04-07] Zirconium

(1)As-received Zircaloy-4 cladding tube

[2M08-12] Reactor Pressure Vessel

Authentication

(1)Neutron and Helium Implantation Test for B₄C-based Ceramics

(2)Fabrication and Evaluation of Highly Controlled Microstructure in B₄C Neutron Absorber by Magnetic Field-Assisted Colloidal Processing

(3)Post-Irradiation Microstructure Evaluation of "Joyo" Irradiated B₄C Control Materials