Oral presentation

[1D01-04] Zirconium Alloys

Mon. Mar 26, 2018 10:00 AM - 11:00 AM Room D (R1-212 -R1 Building)

Chair: Kan Sakamoto (NFD)

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10:00 AM - 10:15 AM

[1D01] A Comparative Study of Deformation Behavior of Zr-1.8Nb Cladding Tube Under Axial and Hoop Stress

*Zishou Zhao¹, Zhengang Duan², Jingjie Shen¹, John Patrick McGgrady¹, Huilong Yang¹, Sho Kano¹, Hiroaki Abe¹ (1. The University of Tokyo, Graduate School of Engineering, 2. Tohoku University, Graduate School of Engineering)

10:15 AM - 10:30 AM

[1D02] Combinatorial effect on irradiation and hydrogenation in fuel cladding tube material

*Sho Kano¹, Huilong Yang¹, Jingjie Shen¹, Zishou Zhao¹, John Patrick McGrady¹, Yoshinori Etoh², Hiroaki Abe¹ (1. The University of Tokyo, 2. Nippon Nuclear Fuel Development Co., Ltd.)

10:30 AM - 10:45 AM

[1D03] Interaction between Microstructural Change by Ion Irradiation and Hydrogen in Zircaloy-2

*Yoshiki Saita¹, Katsuhito Takahashi¹, Hideo Watanabe² (1. Interdisciplinary Graduate School of Engneering Sciences, Kyushu Univ., 2. Research Institute for Applied Mechanics, Kyushu Univ.)

10:45 AM - 11:00 AM

[1D04] Research and Development of RBWR for High Efficiency Transuranium Elements Burner

(5)Crystallographic Analysis of Hydride Formation in Zirconium Alloy by Electron Backscatter Diffraction

*Yun Wang¹, Katsuhito Takahashi¹, Hideo Watanabe² (1. Hitachi,Ltd., 2. Kyushu University)

Oral presentation

[1D05-08] Corrosion

Mon. Mar 26, 2018 11:00 AM - 12:00 PM Room D (R1-212 -R1 Building)

Chair: Yoshiyuki Kaji (JAEA)

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11:00 AM - 11:15 AM

[1D05] SCC growth behavior of SUS630 in high temperature water

(1)Effect of precipitation hardening heat treatment, thermal aging and test temperature

*Takuyo Yamada¹, Takumi Terachi¹, Makie Okamoto¹, Koji Arioka¹ (1. Institute of nuclear safety system, inc.)

11:15 AM - 11:30 AM

[1D06] Mechanistic study for PWSCC in Alloy 690

Influence of cold work on cavity formation rate

*Takumi Terachi¹, Takuyo Yamada¹, Makie Okamoto¹, Koji Arioka¹ (1. INSS)

11:30 AM - 11:45 AM

[1D07] Corrosion behavior of Ni-based alloy in molten FLiNaK salt as a fundamental research on Molten Salt Reactors

*Koji Ogasawara¹, Yuma Sekiguchi¹, Takayuki Terai¹, Hiroshi Kawamura², Kunihiko Tsuchiya³, Takashi Watanabe⁴ (1. The Univ. of Tokyo, 2. Chiyoda Technol, 3. JAEA, 4. NIFS)

11:45 AM - 12:00 PM

[1D08] Radiation effects of ADS target window materials on liquid metal corrosion

*Nariaki Okubo¹, Keietsu Kondo¹, Akane Kitamura¹, Yasuki Okuno¹ (1. Japan Atomic Energy Agency)

Oral presentation

[1D09-11] Next-Gen. Materials (ODS Steels)

Mon. Mar 26, 2018 2:45 PM - 3:35 PM Room D (R1-212 -R1 Building)

Chair: Takeshi Toyama (Tohoku Univ.)

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2:45 PM - 3:00 PM

[1D09] Development of FeCrAl-ODS ferritic steel with cerium oxide dispersion to accident tolerant fuel cladding

(1)Behavior at normal operation and accidents

*Kan Sakamoto¹, Atsushi Ouchi¹, Katsuhito Takahashi¹, Mutsumi Hirai¹, Masaki Aomi², Hiroki Shibata³, Shigeharu Ukai³ (1. NFD, 2. GNF-J, 3. Hokkaido Uni.)

3:00 PM - 3:15 PM

[1D10] Development of FeCrAl-ODS ferritic steel with cerium oxide dispersion to accident tolerant fuel cladding

(2)Mechanical properties evaluation

*Hiroki Shibata¹, Shigeharu Ukai¹, Naoko H. Oono¹, Shigenari Hayashi¹, Kan Sakamoto², Mutsumi Hirai² (1. Hokkaido Univ., 2. NFD)

3:15 PM - 3:30 PM

[1D11] High temperature reaction between metal borides and stainless steel

*Kenichi Hashizume¹, Yusuke Kido¹, Ippei Goto², Kan Sakamoto³ (1. Kyushu Univ., 2. Kyushu Univ. Dept. Eng., 3. NFD)

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

Oral presentation

[1D12-17] Radiation Effects

Mon. Mar 26, 2018 3:35 PM - 5:10 PM Room D (R1-212 -R1 Building)

Chair: Taira Okita (Univ. of Tokyo)

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3:35 PM - 3:50 PM

[1D12] Effects of ion irradiation on PRV mock up material of Hamaoka 1 reactor

*Hideo Watanabe¹, Yasuhiro Kamada², Hideki Yuya³ (1. Kyushu Univ., 2. Iwate Univ., 3. Chubu Denryoku)

3:50 PM - 4:05 PM

[1D13] Electron-irradiation effects on diffusivity of Cu in Fe

*Takeshi Toyama¹, Zhao Can¹, Toshimasa Yoshiie^2,1, Masaki Shimodaira¹, Yasuo Shimizu¹, Koji Inoue¹, Yasuyoshi Nagai¹ (1. IMR, Tohoku Univ., 2. ONSA)

4:05 PM - 4:20 PM

[1D14] In-situ TEM observation of radiation defects in iron-based model alloys under ion irradiation

*Kenta Murakami¹, Dong Yue Chen², Liang Chen², Hiroaki Abe², Naoto Sekimura², Masahide Suzuki¹ (1. Nagaoka University of Technology, 2. The University of Tokyo)

4:20 PM - 4:35 PM

[1D15] Effects of copper concentration and dose rate on low-temperature irradiation embrittlement of carbon steel

*Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹, Masahiro Kawakubo² (1. Instuitute of Nuclear Safety System, 2. Radioactive Waste Management Funding and Research Center)

4:35 PM - 4:50 PM

[1D16] Influence of Si cluster on ion radiation of Microstructure of SS316 steel model alloy

*Takeshi Doi¹, Ken-ichi Fukumoto², Katsuhiko Fujii³, Terumitsu Miura³, Takashi Onitsuka² (1. Fukui Univ, 2. Research institute for nuclear engineering, 3. Institute of Nuclear Safety System)

4:50 PM - 5:05 PM

[1D17] Evaluation status of damage behavior in mercury target vessel of spallation neutron source

*Eiichi Wakai¹, Takashi Naoe¹, Takashi Wakui¹, Masahide Harada¹, Wenhai Guan¹, Kastuhiro Haga¹, Hiroshi Takada¹ (1. JAEA J-PARC)

Time reserved for Chair （5:05 PM - 5:10 PM）

Oral presentation

[1D18-20] Modeling

Mon. Mar 26, 2018 5:10 PM - 6:00 PM Room D (R1-212 -R1 Building)

Chair: Naoyuki Hashimoto (Hokkaido Univ.)

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5:10 PM - 5:25 PM

[1D18] MD simulations to quantify the interaction between a void and dislocation in FCC metals

Kohei Doihara², *Taira Okita¹, Mitsuhiro Itakura³ (1. Research into Artifacts, Center for Engineering, the University of Tokyo, 2. School of Engineering, the University of Tokyo, 3. CCSE JAEA)

5:25 PM - 5:40 PM

[1D19] Three-dimensional motion of a cluster of self-interstitial atoms in bcc iron

*Sho Hayakawa¹, Taira Okita², Mitsuhiro Itakura³, Haixuan Xu⁴, Yuri Osetsky⁵ (1. School of Engineering, University of Tokyo, 2. Research into Artifacts, Center for Engineering, University of Tokyo, 3. Center for Computational Science & e-Systems, Japan Atomic Energy Agency, 4. University of Tennessee, 5. Oak Ridge National Laboratory)

5:40 PM - 5:55 PM

[1D20] Multiscale Modeling of Neutron Irradiation Embrittlement of Reactor Vessel Steel

*Toshiki Nakasuji¹, Yuting Chen¹, Kazunori Morishita¹ (1. Kyoto university)

Time reserved for Chair （5:55 PM - 6:00 PM）

Oral presentation

[2D01-02] Miniature Test

Tue. Mar 27, 2018 9:30 AM - 10:05 AM Room D (R1-212 -R1 Building)

Chair: Masato Yamamoto (CRIEPI)

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9:30 AM - 9:45 AM

[2D01] Investigation of mechanical characterization method with miniature specimen

Applicability of automated ball indentation test to pressure vessel steel

*Satoshi Miyashiro¹, Yuji Kitsunai¹, Masao Itatani², Tetsushi Yamaoka², Tetsuya Toyota³, Takahiro Ishizaki⁴ (1. Nippon Nuclear Fuel Development, 2. Toshiba Energy Systems & Solutions Corporation, 3. Hitachi-GE Nuclear Energy, 4. Hitachi)

9:45 AM - 10:00 AM

[2D02] Application of sub-size Charpy specimen for RPV surveillance test.

*Yoshiyuki Kawaharada¹, Yuji Kitsunai¹, Atsushi Taniguchi², Kensuke Monma², Takayuki Kaminaga², Tetsuya Toyota³, Masaki Wada³, Takahiro Ishizaki⁴ (1. Nippon Nuclear Fuel Development, 2. Tokyo Electric Power Company, 3. Hitachi-GE Nuclear Energy, 4. Hitachi)

Time reserved for Chair （10:00 AM - 10:05 AM）

Oral presentation

[2D03-05] Next-Gen. Materials (SiC)

Tue. Mar 27, 2018 10:05 AM - 10:55 AM Room D (R1-212 -R1 Building)

Chair: Hiroaki Abe (Univ. of Tokyo)

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10:05 AM - 10:20 AM

[2D03] Neutron Irradiation Effects of NITE-SiC/SiC Joint Brazed by Ti-Zr-Cu System

*Naofumi Nakazato¹, Hirotatsu Kishimoto¹, Joon-Soo Park¹, Yuuki Asakura², Akira Kohyama³ (1. Muroran Institute of Technology, 2. Tokyo University of Agriculture and Technology, 3. NITE corporation)

10:20 AM - 10:35 AM

[2D04] Development of SiC/SiC cladding tube for LWR

*Naoya Toumatsu¹, Takashi Takagi¹, Akihide Kawaguchi¹, Takashi Ito¹, Masaru Ukai², Shoko Suyama², Megumi Akimoto² (1. IBIDEN CO.,LTD., 2. Toshiba Energy Systems & Solutions Corporation)

10:35 AM - 10:50 AM

[2D05] Severe accident analysis for core fuel with SiC cladding

(3)Study of cooling effect of circulation steam flow in RPV by nuclear thermal hydraulics analysis code TRACT^TM

*Kenya Takiwaki¹, Yutaka Takeuchi¹, Hideki Horie¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. TOSHIBA ENERGY SYSTEMS & SOLUTIONS CORPORATION)

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

Sessions

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[1D01-04] Zirconium Alloys

(5)Crystallographic Analysis of Hydride Formation in Zirconium Alloy by Electron Backscatter Diffraction

[1D05-08] Corrosion

(1)Effect of precipitation hardening heat treatment, thermal aging and test temperature

Influence of cold work on cavity formation rate

[1D09-11] Next-Gen. Materials (ODS Steels)

(1)Behavior at normal operation and accidents

(2)Mechanical properties evaluation

[1D12-17] Radiation Effects

[1D18-20] Modeling

[2D01-02] Miniature Test

Applicability of automated ball indentation test to pressure vessel steel

[2D03-05] Next-Gen. Materials (SiC)

(3)Study of cooling effect of circulation steam flow in RPV by nuclear thermal hydraulics analysis code TRACTTM

Authentication

(3)Study of cooling effect of circulation steam flow in RPV by nuclear thermal hydraulics analysis code TRACT^TM