Oral presentation

[2E01-06] Irradiation Effect

Thu. Sep 8, 2022 9:45 AM - 11:25 AM Room E (E1 Bildg.2F No.24)

Chair:Naoyuki Hashimoto(Hokkaido Univ.)

9:45 AM - 10:00 AM

[2E01] Investigating the Impact of Non-normalized Atom Probe Tomography Measurements and its Standardization

*Daoyu Pan¹, Kenta Murakami¹, Dongyue Chen¹, Naoto Sekimura¹ (1. UTokyo)

10:00 AM - 10:15 AM

[2E02] Ion-irradiation Effects on Microstructures in RPV Model Alloys with Higher Mn-Ni-Si Concentrations

*XINRUN CHEN¹, NGUYEN Ba Vu Chinh¹, Kenta Murakami² (1. Nagaoka University of Technology, 2. The University of Tokyo)

10:15 AM - 10:30 AM

[2E03] Statistical analysis of Ni and Si co-clustering in stainless steels irradiated to low dose

*Dongyue Chen¹, Kenta Murakami¹, Kenji Dohi², Kenji Nishida², Naoto Sekimura¹ (1. UTokyo, 2. CRIEPI)

10:30 AM - 10:45 AM

[2E04] Uncertainty evaluation of Charpy ductile-to-brittle transition temperature

*Hisashi Takamizawa¹, Yutaka Nishiyama¹ (1. JAEA)

10:45 AM - 11:00 AM

[2E05] Influence of radiation-induced segregation and formation of cavities on grain boundary fracture of stainless steels

*Terumitsu Miura¹, Kenta Murakami², Katsuhiko Fujii¹, Koji Fukuya¹ (1. Institute of Nuclear Safety System, 2. The University of Tokyo)

11:00 AM - 11:15 AM

[2E06] Irradiation Induced Defects Analysis in the Heat Affected Zone of a Reactor Pressure Vessel Steel by Transmission Electron Microscopy

*Masaki Shimodaira¹, Yoosung Ha¹, Hisashi Takamizawa¹, Hitoshi Seto², Jinya Katsuyama¹ (1. JAEA, 2. NFD)

Time reserved for Chair （11:15 AM - 11:25 AM）

Oral presentation

[2E07-08] Corrosion

Thu. Sep 8, 2022 11:25 AM - 12:00 PM Room E (E1 Bildg.2F No.24)

Chair:Chikashi Suzuki(JAEA)

11:25 AM - 11:40 AM

[2E07] Time dependence on corrosion of irradiated austenitic stainless steel weld metals in simulated PWR primary water

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

11:40 AM - 11:55 AM

[2E08] SCC initiation test of cold worked Alloy 690TT under simulated PWR primary water

Crack initiation of cavity induced specimens prior to SCC initiation test

*Toru Oumaya¹, Takumi Terachi², Takuyo Yamada¹, Kohei Kokutani¹, Koji Arioka¹ (1. Institute of Nuclear Safety System, Incorporated, 2. The Kansai Electric Power Company, Incorporated)

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

Oral presentation

[2E09-12] Cladding Materials

Thu. Sep 8, 2022 2:45 PM - 3:55 PM Room E (E1 Bildg.2F No.24)

Chair:Hiroaki ABE(UTokyo)

2:45 PM - 3:00 PM

[2E09] Irradiation Effect on Fracture Properties of LPS and CVD SiC

*Baopu WANG¹, Yansong ZHONG¹, Yina DU¹, Bo HUANG, Kanjiro KAWASAKI¹, Fujio SHINODA¹, Yasunori HAYASHI¹, Tatsuya HINOKI¹ (1. Kyoto Univ.)

3:00 PM - 3:15 PM

[2E10] Evaluation of irradiation induced hardness and microstructure of Zry-2 under applied stress (1)

*Luwei Xue¹, Katsuhito Takahashi¹, Hideo Watanabe¹ (1. KYUSHU UNIVERSITY)

3:15 PM - 3:30 PM

[2E11] Effect of irradiation induced swelling on fiber/matrix residual stress of liquid phase sintering SiC composites

*Yansong Zhong¹, Baopu Wang¹, Yina Du¹, Bo huang, Kanjiro Kawasaki¹, Fujio Shinoda¹, Yasunori Hayashi¹, Hinoki Tatsuya¹ (1. Kyoto Univ.)

3:30 PM - 3:45 PM

[2E12] Ballooning and burst behavior of pre-hydrided Zirconium alloy fuel cladding tube during loss of coolant accident at spent fuel pool

*Kinya Nakamura¹, Kenta Inagaki¹, Atsushi Ui¹ (1. CRIEPI)

Time reserved for Chair （3:45 PM - 3:55 PM）

Oral presentation

[2E13-14] Analytical Technique

Thu. Sep 8, 2022 3:55 PM - 4:30 PM Room E (E1 Bildg.2F No.24)

Chair:Eiichi Wakai(JAEA)

3:55 PM - 4:10 PM

[2E13] Quantification of local plastic strain by EBSD

(Part I: Influence of measurement accuracy on strain estimation)

*masayuki kamaya¹, Naoko Maekawa¹ (1. INSS)

4:10 PM - 4:25 PM

[2E14] Quantification of local plastic strain by EBSD

(Part II: Influence of grain size on quantification of plastic strain)

*Naoko Maekawa¹, Masayuki Kamaya¹ (1. Institute of Nuclear Safety System, Inc.)

Time reserved for Chair （4:25 PM - 4:30 PM）

Oral presentation

[2E15-19] High Entropy Alloys

Thu. Sep 8, 2022 4:30 PM - 5:55 PM Room E (E1 Bildg.2F No.24)

Chair:Sho Kano(UTokyo)

4:30 PM - 4:45 PM

[2E15] Development of new reduced activation HEAs by additive manufacturing methodⅡ

(1) Outline

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

4:45 PM - 5:00 PM

[2E16] Development of new reduced activation HEAs by additive manufacturing method Ⅱ

(2) Material property of additively manufactured alloys

*Hiroshi Oka¹, Motoki Sato¹, Naoyuki Hashimoto¹, Shigehito Isobe¹, Shigenari Hayashi¹, Mikito Ueda¹, Shinichiro Yamashita² (1. Hokkaido Univ., 2. JAEA)

5:00 PM - 5:15 PM

[2E17] Development of new reduced activation HEAs by additive manufacturing methodⅡ

(3) Radiation property

*Shinichiro Yamashita¹, Ikuo Ioka¹, Yosuke Abe¹, Hiroshi Oka², Shigehito Isobe², Naoyuki Hashimoto² (1. Japan Atomic Energy Agency, 2. Hokkaido Univ.)

5:15 PM - 5:30 PM

[2E18] Development of new reduced activation HEAs by additive manufacturing method II

(4) Effect of alloying elements and magnetism on stacking fault energy

*Mitsuhiro Itakura¹, Tomohito Tsuru¹, Shin-ichiro Yamashita¹, Naoyuki Hashimoto² (1. JAEA, 2. Hokkaido Univ.)

5:30 PM - 5:45 PM

[2E19] Characterization of Iron-Based High-Entropy Alloy

*Eiichi Wakai¹, Tamaki Shibayama², Hiroyuki Noto³, Takashi Wakui¹ (1. JAEA, 2. Hokkaido Univ., 3. NIFS)

Time reserved for Chair （5:45 PM - 5:55 PM）

Oral presentation

[3E01-08] Accident Tolerant Fuel

Fri. Sep 9, 2022 9:45 AM - 11:55 AM Room E (E1 Bildg.2F No.24)

Chair:Kinya Nakamura(CRIEPI)

9:45 AM - 10:00 AM

[3E01] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(1) Experimental and Theoretical Investigation of Hydrogen Generation on Cr Surface

*Hiroaki ABE¹, Kazuhiro TAKANABE¹, Akira NAKAYAMA¹, Masatake Yamaguchi², Huilong YANG¹, Sho KANO¹ (1. The University of Tokyo, 2. JAEA)

10:00 AM - 10:15 AM

[3E02] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(2) Alloy design based on first-principles

*Ying Chen¹, Davey Theresa¹, Jovellana John², Yang Huilong², Kano Sho², Abe Hiroaki² (1. Tohoku Univ., 2. UTokyo)

10:15 AM - 10:30 AM

[3E03] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(3) Cr/Zry interface by diffusion bonding

*Bo LI¹, Huilong YANG¹, Reuben Holmes¹, Lijuan CUI¹, Sho KANO¹, Hiroaki ABE¹ (1. UTokyo)

10:30 AM - 10:45 AM

[3E04] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(4) Radiation-induced phase transformation by ion irradiation at Cr/Zry interface

*Sho Kano¹, Huilong Yang¹, Lijuan Cui¹, Hiroaki Abe¹ (1. UTokyo)

10:45 AM - 11:00 AM

[3E05] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(5) Irradiation damage in pure chromium

*Lijuan Cui¹, Yang Huilong¹, Kano Sho¹, Abe Hiroaki¹ (1. UTokyo)

11:00 AM - 11:15 AM

[3E06] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(6) Effects of hydrogen on hoop properties in Zircaloy cladding using Advanced Expansion Due to Compression method

*Neli Sashkova Nikolova¹, Huilong Yang¹, Sho Kano¹, Hiroaki Abe¹ (1. University of Tokyo)

11:15 AM - 11:30 AM

[3E07] Development of Cr-Coated Zircaloy for Accident Tolerant Fuels

(7) Experiment of in-situ observation for mechanical test of Cr/Zry double layered material

*Koichi Ogata¹, Yasunari Shinohara¹, Huilong Yang², Sho Kano², Hiroaki Abe² (1. NDC, 2. UTokyo)

11:30 AM - 11:45 AM

[3E08] Evaluation on thermodynamic properies of Cs-B-O compounds using DFT and lattice vibration calculations

*Chikashi Suzuki¹ (1. JAEA)

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

Sessions

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

[2E01-06] Irradiation Effect

[2E07-08] Corrosion

Crack initiation of cavity induced specimens prior to SCC initiation test

[2E09-12] Cladding Materials

[2E13-14] Analytical Technique

(Part I: Influence of measurement accuracy on strain estimation)

(Part II: Influence of grain size on quantification of plastic strain)

[2E15-19] High Entropy Alloys

(1) Outline

(2) Material property of additively manufactured alloys

(3) Radiation property

(4) Effect of alloying elements and magnetism on stacking fault energy

[3E01-08] Accident Tolerant Fuel

(1) Experimental and Theoretical Investigation of Hydrogen Generation on Cr Surface

(2) Alloy design based on first-principles

(3) Cr/Zry interface by diffusion bonding

(4) Radiation-induced phase transformation by ion irradiation at Cr/Zry interface

(5) Irradiation damage in pure chromium

(6) Effects of hydrogen on hoop properties in Zircaloy cladding using Advanced Expansion Due to Compression method

(7) Experiment of in-situ observation for mechanical test of Cr/Zry double layered material

Authentication