Oral presentation

[2D14-16] 3D Printing

Thu. Sep 9, 2021 4:10 PM - 5:05 PM Room D

chair: Kenta Murakami (UTokyo)

4:10 PM - 4:25 PM

[2D14] Development of new reduced activation HEAs by additive manufacturing method

(1)Outline

*Naoyuki Hashimoto¹, Mikito Ueda¹, Shigenari Hayashi¹, Hiroshi Oka¹, Shigehito Isobe¹, Shinichiro Yamashita², Mitsuhiro Itakura², Tomohito Tsuru² (1. Hokkaido University, 2. JAEA)

4:25 PM - 4:40 PM

[2D15] Development of new reduced activation HEAs by additive manufacturing method

(2)Material property of additively manufactured alloys

*Hiroshi Oka¹, Motoki Satoh¹, Naoyuki Hashimoto¹, Shigehito Isobe¹, Shinichiro Yamashita² (1. Hokkaido Univ., 2. JAEA)

4:40 PM - 4:55 PM

[2D16] Development of new reduced activation HEAs by additive manufacturing method

(3)Radiation property

*Shinichiro Yamashita¹, Ikuo Ioka¹, Hiroshi Oka², Shigehito Isobe², Naoyuki Hashimoto² (1. Japan Atomic Energy Agency, 2. Hokkaido Univ.)

Time reserved for Chair （4:55 PM - 5:05 PM）

Oral presentation

[3D01-02] Debris Behavior

Fri. Sep 10, 2021 9:30 AM - 10:10 AM Room D

chair: Shinichiro Yamashita (JAEA)

9:30 AM - 9:45 AM

[3D01] Evaluation on thermodynamic properies of Cs-B-O compounds using DFT calculations

*Chikashi Suzuki¹ (1. JAEA)

9:45 AM - 10:00 AM

[3D02] Investigation of the microstructure and mechanical property of Zr-SUS-B₄C model debris

*Huilong Yang¹, Kenta Murakaki¹, Syo Kano¹, Hiroaki Abe¹ (1. UTokyo)

Time reserved for Chair （10:00 AM - 10:10 AM）

Oral presentation

[3D03-08] Irradiation Effect

Fri. Sep 10, 2021 10:10 AM - 11:55 AM Room D

chair: Naoyuki Hashimoto (Hokkaido Univ.)

10:10 AM - 10:25 AM

[3D03] Diffusivity of Nickel in Fe under 3MeV Fe Irradiation at 673K Studied by Atom Probe Tomography

*Xinrun Chen¹, Phongsakorn Park Tom¹, Ba Vu Chinh Nguyen¹, Kenta Murakami^1,2 (1. Nagaoka Univ. of Tech., 2. UTokyo)

10:25 AM - 10:40 AM

[3D04] Atom probe tomography analysis of anisotropic distribution of solute elements (Mn, Ni)on irradiated Fe - based model alloy

*Ba Vu Chinh Nguyen¹, Kenta Murakami^2,1, Liang Chen³, Phongsakorn Prak Tom¹ (1. Nagaoka University of Technology, 2. The University of Tokyo, 3. Shianghai Jiao Tong University)

10:40 AM - 10:55 AM

[3D05] Synergistic Effects of Irradiation Flux and Alloy Composition on Point Defect Behaviors by Tracking Loop Nucleation and Growth

*Dongyue Chen¹, Kenta Murakami¹, Huilong Yang¹, Liang Chen², Hiroaki Abe¹, Naoto Sekimura¹ (1. UTokyo, 2. Shanghai Jiao Tong University)

10:55 AM - 11:10 AM

[3D06] Study of irradiation hardening mechanism due to solute atom cluster in a SUS steel

*Ken-ichi Fukumoto¹, Takaaki Mabuchi¹, Katsuhiko Fujii² (1. RINE/Univ. of Fukui, 2. INSS)

11:10 AM - 11:25 AM

[3D07] Rate theory analysis of material damage process under neutron irradiation

*Liangfan Zhu¹, Kazunori Morishita¹, Yoshiyuki Watanabe² (1. Kyoto Univ., 2. QST)

11:25 AM - 11:40 AM

[3D08] Molecular dynamics evaluation of the irradiation effects on nano-scale crack propagation

*Tatsuya Toyoda¹, Xiaoyong Ruan^1,2, Kazunori Morishita¹, Kiyohiro Yabuuchi¹ (1. Kyoto Univ., 2. QST)

Time reserved for Chair （11:40 AM - 11:55 AM）

Oral presentation

[3D09-12] PWSCC

Fri. Sep 10, 2021 2:45 PM - 4:00 PM Room D

chair: Hiroaki Abe (UTokyo)

2:45 PM - 3:00 PM

[3D09] SCC initiation of cold worked Alloy 690TT under simulated PWR primary water

Crack initiation under highly stressed condition accompanying plastic deformation

*Toru Oumaya¹, Takumi Terachi², Takuyo Yamada¹, Kohei Kokutani¹, Koji Arioka¹ (1. INSS, 2. KEPCO)

3:00 PM - 3:15 PM

[3D10] Effect of microstructure on SCC growth behavior of thermal aged SUS630 in high-temperature water

*Takuyo Yamada¹, Kohei Kokutani¹, Toru Oumaya¹, Koji Arioka¹ (1. INSS)

3:15 PM - 3:30 PM

[3D11] Relation between grain boundary oxidation and IASCC initiation of neutron-irradiated stainless steels under simulated PWR primary water conditions

*Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹ (1. INSS)

3:30 PM - 3:45 PM

[3D12] Effects of thermal aging and irradiation on corrosion behavior of austenitic stainless steel weld metals

*Katsuhiko Fujii¹, Takuyo Yamada¹, Kohei Kokutani¹, Koji Fukuya¹ (1. INSS)

Time reserved for Chair （3:45 PM - 4:00 PM）

Oral presentation

[3D13-16] Zircalloy

Fri. Sep 10, 2021 4:00 PM - 5:15 PM Room D

chair: Ken-Ichi Fukumoto (Univ. of Fukui)

4:00 PM - 4:15 PM

[3D13] In-situ TEM observation of the dissolution and re-precipitation behavior of hydrides in Zircaloy-4

*Simian Liu^1,2, Huilong Yang¹, Sho Kano¹, Hiroaki Abe¹ (1. UTokyo, 2. Xi'an Jiaotong Univ)

4:15 PM - 4:30 PM

[3D14] High Temperature Hoop Deformation of Zircaloy- 4 Nuclear Fuel Cladding using Advanced Expansion due to Compression Test

*Neli Sashkova Nikolova¹, Huilong Yang¹, Sho Kano¹, Hiroaki Abe¹ (1. UTokyo)

4:30 PM - 4:45 PM

[3D15] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(1)Summary and Plan of the Project

*Hiroaki Abe¹, Sho Kano¹, Huilong Yang¹, Kazuhiro Takanabe¹, Akira Nakayama¹, Ying Chen², Masatake Yamaguchi³, Yasunari Shinohara⁴, Koichi Ogata⁴ (1. The University of Tokyo, 2. Tohoku University, 3. JAEA, 4. NDC)

4:45 PM - 5:00 PM

[3D16] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(2)Materials Development and Radiation Effects

*Sho Kano¹, Kenta Murakami^1,2, Huilong Yang¹, Kazuhiro Takanabe¹, Akira Nakayama¹, Ying Chen³, Masataka Yamaguchi⁴, Yasunari Shinohara⁵, Koichi Ogata⁵, Hiroaki Abe¹ (1. UTokyo, 2. Nagaoka Univ. of Tech., 3. Tohoku Univ., 4. JAEA, 5. NDC)

Time reserved for Chair （5:00 PM - 5:15 PM）

Sessions

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

[2D14-16] 3D Printing

[2D14] Development of new reduced activation HEAs by additive manufacturing method

(1)Outline

[2D15] Development of new reduced activation HEAs by additive manufacturing method

(2)Material property of additively manufactured alloys

[2D16] Development of new reduced activation HEAs by additive manufacturing method

(3)Radiation property

[3D01-02] Debris Behavior

[3D01] Evaluation on thermodynamic properies of Cs-B-O compounds using DFT calculations

[3D02] Investigation of the microstructure and mechanical property of Zr-SUS-B₄C model debris

[3D03-08] Irradiation Effect

[3D03] Diffusivity of Nickel in Fe under 3MeV Fe Irradiation at 673K Studied by Atom Probe Tomography

[3D04] Atom probe tomography analysis of anisotropic distribution of solute elements (Mn, Ni)on irradiated Fe - based model alloy

[3D05] Synergistic Effects of Irradiation Flux and Alloy Composition on Point Defect Behaviors by Tracking Loop Nucleation and Growth

[3D06] Study of irradiation hardening mechanism due to solute atom cluster in a SUS steel

[3D07] Rate theory analysis of material damage process under neutron irradiation

[3D08] Molecular dynamics evaluation of the irradiation effects on nano-scale crack propagation

[3D09-12] PWSCC

[3D09] SCC initiation of cold worked Alloy 690TT under simulated PWR primary water

Crack initiation under highly stressed condition accompanying plastic deformation

[3D10] Effect of microstructure on SCC growth behavior of thermal aged SUS630 in high-temperature water

[3D11] Relation between grain boundary oxidation and IASCC initiation of neutron-irradiated stainless steels under simulated PWR primary water conditions

[3D12] Effects of thermal aging and irradiation on corrosion behavior of austenitic stainless steel weld metals

[3D13-16] Zircalloy

[3D13] In-situ TEM observation of the dissolution and re-precipitation behavior of hydrides in Zircaloy-4

[3D14] High Temperature Hoop Deformation of Zircaloy- 4 Nuclear Fuel Cladding using Advanced Expansion due to Compression Test

[3D15] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(1)Summary and Plan of the Project

[3D16] Development of Metal-Coated Zircaloy for Accident Tolerant Fuel

(2)Materials Development and Radiation Effects

Authentication