Oral presentation

[2C10-15] Debris

Wed. Mar 27, 2024 2:45 PM - 4:25 PM Room C (21Bildg.2F 21-205)

Chair:Kinya Nakamura(CRIEPI)

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2:45 PM - 3:00 PM

[2C10] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(1)Outline

*Masayoshi UNO¹, Ohishi Yuuji², Kobayashi Yoshinaohinao³, Ueda Shigeru⁴, Nagae Yuji⁵ (1. University of Fukui, 2. Osaka Univ., 3. Tokyo Tech., 4. Tohoku Univ., 5. JAEA)

3:00 PM - 3:15 PM

[2C11] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(2)Preparation and observation of simulated fine particles.

*Tomoki Yoshiawa¹, Keisuke Niino¹, Shuto Tanaka¹, Yuji Arita¹ (1. Univ. Fukui)

3:15 PM - 3:30 PM

[2C12] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(3)Experimental Verification of Solidification Path Diagram Created from Debris Sampling Data

*Yusuke Akimoto¹, Masayoshi Uno¹, Takashi Onitsuka¹ (1. Univ. of Fukui)

3:30 PM - 3:45 PM

[2C13] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(4)Metallic debris formation mechanism by interaction between molten Fe-Zr alloy and stainless steel

*Ayumi Itoh¹ (1. Tokyo Tech)

3:45 PM - 4:00 PM

[2C14] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(5)Damage behavior of lower plenum due to reaction with metallic debris

*Takumi Sato¹, Kenta Shimomura¹, Yuji Nagae¹ (1. Core Status Evaluation Group, JAEA)

4:00 PM - 4:15 PM

[2C15] Clarification of Debris Formation Conditions on the Basis of the Sampling Data and Experimental Study Using Simulated Fuel Debris

(6)Evaluation of damage by reaction between metallic debris and structural materials in lower plenum

*Yuji Nagae¹, Takumi Sato¹, Ayumi Itho², Shigeru Ueda³ (1. JAEA, 2. Tokyo Tech, 3. Tohoku Univ.)

Time reserved for Chair （4:15 PM - 4:25 PM）

Oral presentation

[2C16-21] Nuclear Materials

Wed. Mar 27, 2024 4:25 PM - 6:00 PM Room C (21Bildg.2F 21-205)

Chair:Shinichiro Yamashita(JAEA)

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4:25 PM - 4:40 PM

[2C16] Phase separation and recombinaison in U₁₋_yPu_yO₂₋_x with y = 0.30, 0.45, and 1.00

*Romain Jean-Marie Vauchy¹, Masahiro Ogasawara², Tadahisa Yamada², Takeo Sunaoshi², Tetsuya Tamura², Yuta Horii¹, Shun Hirooka¹, Masato Kato¹, Tatsutoshi Murakami¹ (1. Japan Atomic Energy Agency, 2. Inspection Development Company)

4:40 PM - 4:55 PM

[2C17] Development of accident tolerant control rod

(7) Compatibility between novel neutron absorbers and molten fuel at high temperature

*Kinya Nakamura¹, Hirokazu Ohta¹, Masahide Takano² (1. CRIEPI, 2. JAEA)

4:55 PM - 5:10 PM

[2C18] Development of Accident Tolerant Core Materials (1)

Development of Cladding Materials for Early Commercialization ~ Core Materials for Further Safety Improvement

*Soichiro Yamaguchi¹, Tetsuro Yamaoka¹, Toshiki Nishimura¹, Shoko Suyama¹, Masao Owaki¹, Fumiaki Inoue¹ (1. TOSHIBA ESS)

5:10 PM - 5:25 PM

[2C19] Effect of constituents on application conditions of silicon carbide composites

*Tatsuya Hinoki¹, Yansong Zhong¹, Junyeab Lee¹ (1. Kyoto University)

5:25 PM - 5:40 PM

[2C20] Modeling of SiC materials for nuclear energy based on first principles calculations

*Baopu WANG¹, Liangfan Zhu¹, Yuting Chen¹, Hirotomo Iwakiri², Kazunori Morishita¹ (1. Kyoto Univ., 2. Ryukyus Univ.)

5:40 PM - 5:55 PM

[2C21] In search for radiation-resistant high entropy alloys composed by light metal elements

(1) Introduction of the research project

*Kenta Murakami¹, Xinrun Chen², Kin Tan², Tatsuya Suzuki² (1. UTokyo, 2. Nagaoka Univ. of Tech.)

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

Oral presentation

[3C01-05] Irradiation Effects

Thu. Mar 28, 2024 9:30 AM - 10:55 AM Room C (21Bildg.2F 21-205)

Chair:Tatsuya Hinoki(Kyoto Univ.)

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9:30 AM - 9:45 AM

[3C01] Effect of irradiation temperature on Mn-Ni-Si clusters in RPV model alloys

*Xinrun Chen¹, Tatsuya Suzuki¹, Ba Vu Chinh NGUYEN⁴, Takeshi Toyama³, Koji Inoue³, Sho Kano², Kenta Murakami² (1. Nagaoka University of Technology, 2. The University of Tokyo, 3. Tohoku University, 4. The University of Danang)

9:45 AM - 10:00 AM

[3C02] Change in Local Mechanical Properties of Model Alloys for Reactor Pressure Vessel Steel by Fe Ion Irradiation.

*Yuuki Maeda¹, Katsuhiko Fujii¹, Koji Fukuya¹ (1. INSS)

10:00 AM - 10:15 AM

[3C03] Distribution of Cationic Disordering in Spinel Structure induced on Swift Heavy Ion Irradiations

*Satoru Yoshioka¹, Kazuhiro Yasuda¹, Syo Matsumura², Norito Ishikawa³, Eiichi Kobayashi⁴, Koji Okudaira⁵ (1. Kyushu Univ., 2. NIT, Kurume College, 3. JAEA, 4. SAGA Light Source, 5. Chiba Univ.)

10:15 AM - 10:30 AM

[3C04] Assessment of microstructural evolution in iron during neutron irradiation

*Liangfan Zhu¹, Yuting Chen¹, Sakura Nishikawa¹, Kazunori Morishita¹ (1. Kyoto Univ.)

10:30 AM - 10:45 AM

[3C05] Statistical analysis of large size cluster generation mechanism using molecular dynamics simulation

*Yuting Chen¹, Kazunori Morishita¹ (1. Kyoto Univ.)

Time reserved for Chair （10:45 AM - 10:55 AM）

Oral presentation

[3C06-09] Cladding Coating

Thu. Mar 28, 2024 10:55 AM - 12:00 PM Room C (21Bildg.2F 21-205)

Chair:Kenta Murakami(UTokyo)

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10:55 AM - 11:10 AM

[3C06] Study on coating technic to enhance accident tolerance of fuel cladding

(1) Overview of accident tolerant coating technic studies and apparatus development in JAEA

*Shinichiro Yamashita¹, Afiqa Mohamad¹, Yoshiyuki Nemoto¹, Yasutaka Soma¹, Yasuhiro Ishijima¹, Tomonori Sato¹, Ikuo Ioka¹, Hai vu Pham¹, Shuhei Miwa¹, Kunihisa Nakajima¹ (1. Japan Atomic Energy Agency)

11:10 AM - 11:25 AM

[3C07] Study on coating technic to enhance accident tolerance of fuel cladding

(2) Oxidation and hydriding behavior of the Cr coated Zry4

*Keito Kawai¹, Yosiyuki Nemoto², Shinichiro Yamasita², Yasuhiro Ishijima², Ikuo Ioka², Koudai Funamoto³, Hisao Atsumi¹ (1. Kindai Univ., 2. JAEA, 3. Tocalo)

11:25 AM - 11:40 AM

[3C08] Study on coating technic to enhance accident tolerance of fuel cladding

(3) Irradiation behavior of the Cr coated MDA cladding

*Afiqa Mohamad¹, Chen Jiao¹, Ikuo Ioka¹, Eriko Suzuki¹, Keietsu Kondo¹, Yoshiyuki Nemoto¹, Nariaki Okubo¹, Shinichiro Yamashita¹, Yuji Okada², Daiki Sato² (1. JAEA, 2. MHI)

11:40 AM - 11:55 AM

[3C09] Study on coating technic to enhance accident tolerance of fuel cladding

(4) Oxidation behavior of the TiN/TiAlN multilayer coated Zry4

*Hai Pham¹, Yoshiyuki Nemoto¹, Shinichiro Yamashita¹ (1. JAEA)

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

Oral presentation

[3C10-13] Corrosion

Thu. Mar 28, 2024 2:45 PM - 3:55 PM Room C (21Bildg.2F 21-205)

Chair:Kazunori Morishita(Kyoto Univ.)

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2:45 PM - 3:00 PM

[3C10] Study on corrosion behavior of 316L austenitic steel in Liquid Lead Bismuth Stirred Flow at 1173 K

*Jinkyoung Chung¹, Sota Hagiwara¹, Masatoshi Kondo¹ (1. Tokyo Tech)

3:00 PM - 3:15 PM

[3C11] SCC Initiation and Propagation Mechanisms of Stainless Steel in Simulated PWR primary water

(1) Investigation from Nanoscale Analysis of Crack Tip

*Katsuhiko Fujii¹, Takumi Terachi¹, Takuyo Yamada¹, Koji Arioka¹ (1. INSS)

3:15 PM - 3:30 PM

[3C12] SCC initiation behavior of Alloy 600 in simulated PWR primary water using blunt notch CT specimen

*Takuyo Yamada¹, Takumi Terachi¹, Yuuki Yamaoka¹, Koji Arioka¹ (1. INSS)

3:30 PM - 3:45 PM

[3C13] Corrosion Behavior of Ion-irradiated Zirconium Alloy

*KATSUHITO TAKAHASHI¹, Yasuhisa Aono¹, Takashi Mutaguchi², Shyun Simabukuro², Hideo Watanabe² (1. Hitachi, 2. Kyushu Univ.)

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

Oral presentation

[3C14-14] Evaluation & Analysis

Thu. Mar 28, 2024 3:55 PM - 4:15 PM Room C (21Bildg.2F 21-205)

Chair:Katsuhiko Fujii(INSS)

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3:55 PM - 4:10 PM

[3C14] Development of shear punch test technique for high-temperature strength evaluation of irradiated materials in the form of thin plate

*Yuta Shizukawa¹, Takashi Tanno¹, Yasuhide Yano¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （4:10 PM - 4:15 PM）

Sessions

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

[2C10-15] Debris

(1)Outline

(2)Preparation and observation of simulated fine particles.

(3)Experimental Verification of Solidification Path Diagram Created from Debris Sampling Data

(4)Metallic debris formation mechanism by interaction between molten Fe-Zr alloy and stainless steel

(5)Damage behavior of lower plenum due to reaction with metallic debris

(6)Evaluation of damage by reaction between metallic debris and structural materials in lower plenum

[2C16-21] Nuclear Materials

(7) Compatibility between novel neutron absorbers and molten fuel at high temperature

Development of Cladding Materials for Early Commercialization ~ Core Materials for Further Safety Improvement

(1) Introduction of the research project

[3C01-05] Irradiation Effects

[3C06-09] Cladding Coating

(1) Overview of accident tolerant coating technic studies and apparatus development in JAEA

(2) Oxidation and hydriding behavior of the Cr coated Zry4

(3) Irradiation behavior of the Cr coated MDA cladding

(4) Oxidation behavior of the TiN/TiAlN multilayer coated Zry4

[3C10-13] Corrosion

(1) Investigation from Nanoscale Analysis of Crack Tip

[3C14-14] Evaluation & Analysis

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