Oral presentation

[1C01-03] Severe Accident 1

Wed. Sep 5, 2018 10:00 AM - 10:50 AM Room C (B21 -B Building)

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

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10:00 AM - 10:15 AM

[1C01] Melting behavior of reactor core during severe accident of BWR

(1) Fracture behavior of stainless structure materials by molten metallic and oxidic corium

*Takehiro Sumita¹, Yoshinao Kobayashi¹, Shigeru Ueda², Toshio Nakagiri³ (1. Tokyo Institute of Technology, 2. Tohoku University, 3. JAEA)

10:15 AM - 10:30 AM

[1C02] Melting behavior of reactor core during severe accident of BWR

(2)Liquid phase formation from control blade and channel box

Zheng Lichun¹, Kazuya Hosoi¹, *Shigeru Ueda¹, Xu Gao¹, Shin-ya Kitamrua¹, Yoshinao Kobayashi² (1. IMRAM Tohoku University, 2. LANE Tokyo Institute of Technology)

10:30 AM - 10:45 AM

[1C03] Melting behavior of reactor core during severe accident of BWR

(3)Analysis of accident condition and molten material relocation behavior

*Toshio nakagiri¹, ayako sudo¹, shinji yoshikawa¹, yuta abe¹, ikken sato¹ (1. JAEA)

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

Oral presentation

[1C04-07] Stainless Steel 1

Wed. Sep 5, 2018 10:50 AM - 11:55 AM Room C (B21 -B Building)

Chair:Katsuhiko Fujii(INSS)

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10:50 AM - 11:05 AM

[1C04] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(5) Summary

*Yutaka Watanabe¹, Toshiaki Horiuchi², Satoshi Minamoto³, Hiroshi Abe¹, Masato Koshiishi⁴ (1. Tohoku University, 2. Hokkaido University of Science, 3. NIMS, 4. NFD)

11:05 AM - 11:20 AM

[1C05] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(6)Effects of thrmal aging and neutron irradiation on microstructural changes of stainless steel welds

*Hiroshi Abe¹, Yutaka Watanabe¹, Kazuma Hirata¹, Takamichi Miyazaki¹, Masato Koshiishi⁴, Toshiaki Horiuchi², Satoshi Minamoto³ (1. Tohoku Univ, 2. Hokkaido University of Science, 3. NIMS, 4. NFD)

11:20 AM - 11:35 AM

[1C06] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(7) Development of prediction model for G phase precipitation

*Toshiaki Horiuchi¹, Satoshi Minamoto², Masato Koshiishi³, Hiroshi Abe⁴, Yutaka Watanabe⁴ (1. HUS, 2. NIMS, 3. NFD, 4. Tohoku Univ.)

11:35 AM - 11:50 AM

[1C07] Fundamental technology development for evaluation of thermally ageing embrittlement of stainless steel welds used as pressure boundaries in nuclear power plants

(8) Development of prediction model for spinodal decomposition

*SATOSHI MINAMOTO¹, Toshiaki Horiuchi², Hiroshi Abe³, Yutaka Watanabe³ (1. National Institute for Materials Science, 2. Hokkaido University of science, 3. Tohoku University)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral presentation

[1C08-10] Stainless Steel 2

Wed. Sep 5, 2018 2:45 PM - 3:35 PM Room C (B21 -B Building)

Chair:Yasuhiro Chimi(JAEA)

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2:45 PM - 3:00 PM

[1C08] Localized deformation of stainless steels neutron-irradiated in PWRs

- Comparison between baffle former bolt and flux thimble tube -

*Terumitsu Miura¹, Katsuhiko Fujii¹, Koji Fukuya¹, Yuji Kitsunai² (1. Instuitute of Nuclear Safety System, 2. Nippon Nuclear Fuel Development)

3:00 PM - 3:15 PM

[1C09] Dose dependence of solute clusters in neutron-irradiated 316 stainless steels

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

3:15 PM - 3:30 PM

[1C10] Mechanical Properties and Microstructural Changes of Improved Stainless Steel for JOYO Irradiated Next Generation Reactor

*Mitsutaka Nishimura¹, Ken-ichi Fukumoto³, Hideki Matsui², Takashi Onitsuka³ (1. University of Fukui, 2. Tohoku University, 3. Research Institute of Nuclear Engineering)

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

Oral presentation

[1C11-13] Reactor Pressure Vessel 1

Wed. Sep 5, 2018 3:35 PM - 4:25 PM Room C (B21 -B Building)

Chair:Naoyuki Hashimoto(Hokkaido Univ.)

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3:35 PM - 3:50 PM

[1C11] Physical property measurements and crystallographic analysis of G-phase Ni₁₆Si₇Mn₆

A fundamental study for improving the precision of embrittlement lifetime prediction of reactor pressure vessels

*Yoshitaka Matsukawa¹, Masatake Yamaguchi², Yoshiya Homma¹, Fumihiro Nakamori³, Hiroaki Muta³, Daichi Ito¹, Yuji Ohishi³, Yoshinao Kobayashi⁴ (1. Tohoku University, 2. Japan Atomic Energy Agency, 3. Osaka University, 4. Tokyo Institute of Technology)

3:50 PM - 4:05 PM

[1C12] Microstructure analysis using X-ray absorption on HAZ of ion-irradiated RPV steel

*Yoosung Ha¹, Keiko Iwata¹, Hisashi Takamizawa¹, Yoshihiro Okamoto¹, Iwao Shimoyama¹, Mitsunori Honda¹, Satoshi Hanawa¹, Yutaka Nishiyama¹ (1. JAEA)

4:05 PM - 4:20 PM

[1C13] Irradiation embrittlement of RPV steel model alloys with different Cu,Ni levels and recovery behavior by thermal treatment

*Yusuke Goya¹, Hideo Watanabe², Takuya Yamamoto³, Takuya Tsuru¹ (1. Kyushu Univ, 2. RIAM, Kyushu Univ, 3. University of California, Santa Barbara)

Time reserved for Chair （4:20 PM - 4:25 PM）

Oral presentation

[1C14-17] Reactor Pressure Vessel 2

Wed. Sep 5, 2018 4:25 PM - 5:30 PM Room C (B21 -B Building)

Chair:Koji Fukuya(INSS)

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4:25 PM - 4:40 PM

[1C14] FY2017 Investigation for Improvement of Evaluation Methods of Irradiation Effects on Reactor Pressure Vessel and Core Internals

(1) Through-wall fracture toughness distribution of decommissioned Zion Unit 1 reactor pressure vessel material

*Masato Yamamoto¹, Tomohiro Kobayashi¹ (1. Central Research Institute of Electric Power Industry)

4:40 PM - 4:55 PM

[1C15] FY2017 Investigation for Improvement of Evaluation Methods of Irradiation Effects on Reactor Pressure Vessel and Core Internals

(2) Through-wall microstrcutural changes of decommissioned Zion Unit 1 RPV steel due to neutron irradiation

*Tomohiro Kobayashi¹, Kenji Nishida¹, Masato Yamamoto¹ (1. Central Research Institute of Electric Power Industry)

4:55 PM - 5:10 PM

[1C16] FY2017 investigation for improvement of evaluation methods of irradiation effects on reactor pressure vessel and core internals

(3) Correlation between microstructure and yield strength in neutron irradiated austenitic stainless steels

*Yuichi Miyahara¹, Kenji Nishida¹, Siwei Chen¹, Katsuhiko Fujii² (1. CRIEPI, 2. INSS)

5:10 PM - 5:25 PM

[1C17] FY2017 Investigation for Improvement of Evaluation Methods of Irradiation Effects on Reactor Pressure Vessel and Core Internals

(4) Evaluation of metallographic structure in each part in the thickness direction of JRQ material

*Kenta Nishimoto¹, Tomohiro Kobayashi¹, Masato Yamamoto¹, Kenji Nishida¹, Yasufumi Miura¹ (1. Central Research Institute of Electric Power Industry)

Time reserved for Chair （5:25 PM - 5:30 PM）

Oral presentation

[1C18-19] Severe Accident 2

Wed. Sep 5, 2018 5:30 PM - 6:00 PM Room C (B21 -B Building)

Chair:Nariaki Okubo(JAEA)

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5:30 PM - 5:45 PM

[1C18] Effect of heating during the severe accident on the strength and the microstructure of LWR steels

(1) Estimation of the strength and microstructure of the heat affected reactor containment vessel steel

*Taro Fumimoto¹, Kohei Noguchi¹, Kento Takahashi¹, Shiro Jitsukawa¹ (1. National Institute of Technology, Fukushima College)

5:45 PM - 6:00 PM

[1C19] Estimation of the annealing effect on strength and microstructure of LWR steels during severe accident

(2)Effects of heating on the strength and the microstructure of the reactor materials during severe accident

*Kohei Noguchi¹, Taro Humimoto¹, Yukito Yamashita¹, Shiro Jitsukawa¹ (1. National Institute of Technology, Fukushima College)

Oral presentation

[2C01-03] Corrosion

Thu. Sep 6, 2018 10:00 AM - 10:50 AM Room C (B21 -B Building)

Chair:Katsuhito Takahahsi(NFD)

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10:00 AM - 10:15 AM

[2C01] Property evaluation of Zircaloy oxide by in-situ AC impedance measurement

*Yoko Ikeda¹, Tomofumi Sakuragi², Satoshi Yoshida³ (1. Nippon Steel & Sumikin Technology Co., Ltd, 2. Radioactive Waste Management Funding and Research Center, 3. Kobe Steel, Ltd)

10:15 AM - 10:30 AM

[2C02] Radiation effects of ADS target window material of SS316L on liquid metal corrosion

*Nariaki Okubo¹, Yuki Fujimura¹, Akane Kitamura¹, Yasuki Okuno¹, Keietsu Kondo¹ (1. Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[2C03] Mechanistic study for PWSCC in Alloy 690

Influences of cold work and temperature for deformation in high temperature hydrogen gas

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

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

Oral presentation

[2C04-07] Fuel Cladding Material

Thu. Sep 6, 2018 10:50 AM - 11:55 AM Room C (B21 -B Building)

Chair:Sho Kano(Univ. of Tokyo)

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10:50 AM - 11:05 AM

[2C04] Considerations for the seismic evaluation of the fuel assembly after Loss-of-Coolant-Accident (LOCA) in PWR

(1)Result of four-point-bending tests with a fuel rod cladding exposed to the temperature condition of a postulated LOCA

*Daisuke Komiyama¹, Toshiyuki Ogita² (1. Mitsubishi Nuclear Fuel Co., Ltd, 2. The Kansai Electric Power Co., Inc.)

11:05 AM - 11:20 AM

[2C05] Considerations for the seismic evaluation of the fuel assembly after Loss-of-Coolant-Accident (LOCA) in PWR

(2)Impact behavior of a fuel grid exposed to the temperature condition of a postulated LOCA

Ryo Fukuda¹, Nozomu Murakami¹, *Masaaki Yamato¹, Hisashi Koike², Yasunari Shinohara² (1. Mitsubishi Heavy Industries, Ltd., 2. Nuclear Development Corporation)

11:20 AM - 11:35 AM

[2C06] Feasibility study of eddy current testing for accident tolerant fuel using silicon carbide in light water reactor

*Noriyasu Kobayashi¹, Jun Semboshi¹, Megumi Akimoto¹, Masaru Ukai¹ (1. Toshiba Energy Systems & Solutions)

11:35 AM - 11:50 AM

[2C07] Permeation behavior of tritium through FeCrAl-ODS ferritic steel

*Yudai Urabe¹, Kenichi Hashizume¹, Teppei Otsuka², Kan Sakamoto³ (1. Kyushu Univ., 2. Kindai Univ., 3. NFD)

Time reserved for Chair （11:50 AM - 11:55 AM）

Oral presentation

[2C08-11] Radiation Effect 1

Thu. Sep 6, 2018 2:45 PM - 3:50 PM Room C (B21 -B Building)

Chair:Yoshitaka Matsukawa(Tohoku Univ.)

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2:45 PM - 3:00 PM

[2C08] The Unfaulting of Frank Loops Influenced by Loop Size in Heavy Ion Irradiation

*Dongyue Chen¹, Kenta Murakami², Kenji Dohi³, Kenji Nishida³, Naoto Sekimura¹ (1. The University of Tokyo, 2. Nagaoka University of Technology, 3. Central Research Institute of Electric Power Industry)

3:00 PM - 3:15 PM

[2C09] Microstructure and Hardness Evaluation of Neutron Irradiated Japanese PWR Standard Reference Materials

Tomohiro Kobayashi¹, *Akiyoshi Nomoto¹, Kenji Nishida¹ (1. Central Research Institute of Electric Power Industry)

3:15 PM - 3:30 PM

[2C10] Changes in Tensile Properties of Mn · Ni Addition Model Alloys by Neutron Irradiation

*Takuya Irie¹, Hideo Watanabe², Tomonari Tanaka¹ (1. Kyushu Univ, 2. RIAM,Kyushu Univ)

3:30 PM - 3:45 PM

[2C11] Adsorption behavior of radiocesium of filtered containment venting system during long-term operation

*Moeko Nakata¹, Akihiro Togari¹, Qilai Zhou², Yuji Hatano³, Yasuhisa Oya¹ (1. Grad. Sch., Shizuoka Univ., 2. Fac. of Sci., Shizuoka Univ., 3. HIRC, Univ. of Toyama)

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

Oral presentation

[2C12-16] Radiation Effect 2

Thu. Sep 6, 2018 3:50 PM - 5:10 PM Room C (B21 -B Building)

Chair:Akiyoshi Nomoto(CRIEPI)

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3:50 PM - 4:05 PM

[2C12] Study on reliability and predictability of Bayesian statistical analysis for irradiation embrittlement data

*Hisashi Takamizawa¹, Satoshi Hanawa¹, Yutaka Nishiyama¹ (1. Japan atomic energy agency)

4:05 PM - 4:20 PM

[2C13] Data survey and trend analysis of radiation effects on structural material properties of core internals in light water reactors

(1)Overview

*Yasuhiro Chimi¹, Koji Fukuya², Shigeki Kasahara¹, Katsuhiko Fujii², Satoshi Hanawa¹ (1. JAEA, 2. INSS)

4:20 PM - 4:35 PM

[2C14] Data survey and trend analysis of radiation effects on structural material properties of core internals in light water reactors

(2)Tensile properties and IASCC initiation

*Koji Fukuya¹, Yasuhiro Chimi², Shigeki Kasahara², Katsuhiko Fujii¹, koji Fujimoto³ (1. Institute of Nuclear Safety System, 2. Japan Atomic Energy Agency, 3. Nuclear Development Corporation)

4:35 PM - 4:50 PM

[2C15] Data Survey and Trend Analysis of Radiation Effects on Structural Material Properties of Core Internals in Light Water Reactors

(3) IASCC Propagation and Fracture Toughness

*Shigeki Kasahara¹, Koji Fukuya², Yasuhiro Chimi¹, Katsuhiko Fujii², Masato Koshiishi³ (1. JAEA, 2. INSS, 3. NFD)

4:50 PM - 5:05 PM

[2C16] Risk-based Integrity Assessment of Reactor Pressure Vessel

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

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

Sessions

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

[1C01-03] Severe Accident 1

(1) Fracture behavior of stainless structure materials by molten metallic and oxidic corium

(2)Liquid phase formation from control blade and channel box

(3)Analysis of accident condition and molten material relocation behavior

[1C04-07] Stainless Steel 1

(5) Summary

(6)Effects of thrmal aging and neutron irradiation on microstructural changes of stainless steel welds

(7) Development of prediction model for G phase precipitation

(8) Development of prediction model for spinodal decomposition

[1C08-10] Stainless Steel 2

- Comparison between baffle former bolt and flux thimble tube -

[1C11-13] Reactor Pressure Vessel 1

A fundamental study for improving the precision of embrittlement lifetime prediction of reactor pressure vessels

[1C14-17] Reactor Pressure Vessel 2

(1) Through-wall fracture toughness distribution of decommissioned Zion Unit 1 reactor pressure vessel material

(2) Through-wall microstrcutural changes of decommissioned Zion Unit 1 RPV steel due to neutron irradiation

(3) Correlation between microstructure and yield strength in neutron irradiated austenitic stainless steels

(4) Evaluation of metallographic structure in each part in the thickness direction of JRQ material

[1C18-19] Severe Accident 2

(1) Estimation of the strength and microstructure of the heat affected reactor containment vessel steel

(2)Effects of heating on the strength and the microstructure of the reactor materials during severe accident

[2C01-03] Corrosion

Influences of cold work and temperature for deformation in high temperature hydrogen gas

[2C04-07] Fuel Cladding Material

(1)Result of four-point-bending tests with a fuel rod cladding exposed to the temperature condition of a postulated LOCA

(2)Impact behavior of a fuel grid exposed to the temperature condition of a postulated LOCA

[2C08-11] Radiation Effect 1

[2C12-16] Radiation Effect 2

(1)Overview

(2)Tensile properties and IASCC initiation

(3) IASCC Propagation and Fracture Toughness

Authentication