Oral presentation

[2C01-07] Data Science, Fuel Research with Machine Learning

Thu. Sep 7, 2023 9:30 AM - 11:25 AM Room C (IB Bildg.1F IB015)

Chair:Tatsumi Arima(Kyushu Univ.)

9:30 AM - 9:45 AM

[2C01] New Developments in Nuclear Fuel Research through Integration with Data Science

(1) General Introduction

*Ken Kurosaki^1,2, Yuji Ohishi³, Masato Kato⁴, Tsuyoshi Yaita⁴, Toru Higuchi⁵, Kenji Konashi⁶ (1. Kyoto Univ., 2. Univ. of Fukui, 3. Osaka Univ., 4. JAEA, 5. NFD, 6. Tohoku Univ.)

9:45 AM - 10:00 AM

[2C02] New Developments in Nuclear Fuel Research through Integration with Data Science

(2)Design of machine learning models for highly accurate prediction of thermal conductivity

*Koki Takeichi¹, Ken Kurosaki^1,4, Masaya Kumagai^1,3, Yuji Ohishi² (1. Kyoto Univ., 2. Osaka Univ., 3. SAKURA internet Inc., 4. Univ. of Fukui)

10:00 AM - 10:15 AM

[2C03] New Developments in Nuclear Fuel Research through Integration with Data Science

(3)Development of neural network potential of UO₂

*Kenji Konashi¹, Nobuhiko Kato², Kazuki Mori², Ken Kurosaki³ (1. Tohoku University, 2. CTC, 3. Kyoto University)

10:15 AM - 10:30 AM

[2C04] New Developments in Nuclear Fuel Research through Integration with Data Science

(4) Development of machine-learning gap conductance model

*Masato Kato¹, Tomoyuki Uwaba¹, Masashi Watanabe¹, Shun Hirooka¹, Kenji Konashi², Ken Kurosaki^3,4 (1. JAEA, 2. Tohoku Univ., 3. Kyoto Univ., 4. Univ. of Fukui )

10:30 AM - 10:45 AM

[2C05] New Developments in Nuclear Fuel Research through Integration with Data Science

(5)Fabrication and Characterization of Metallic Uranium Compounds (UFe₃B₂, USiNi) Prepared via Spark Plasma Sintering

*Yifan Sun¹, Yuji Miyawaki², Yuji Ohishi², Hiroaki Muta², Shun Fujieda², Ken Kurosaki^1,3 (1. Kyoto Univ., 2. Osaka Univ., 3. Univ. of Fukui)

10:45 AM - 11:00 AM

[2C06] New Developments in Nuclear Fuel Research through Integration with Data Science

(6) Development of synchrotron radiation XRD measurement system for gas-floating melts

*Tsuyoshi Yaita¹, Tohru Kobayashi¹, Hajime Tanida¹, Yuji Ohishi², Ken Kurosaki³, Kenji Konashi⁴ (1. JAEA, 2. Osaka Univ., 3. Kyoto Univ., 4. Tohoku Univ.)

11:00 AM - 11:15 AM

[2C07] New Developments in Nuclear Fuel Research through Integration with Data Science

(7) Synthesis of Uranium Related Oxide to Verify Thermal Conductivity Predicted by Materials Informatics

*Atsushi Ohuchi¹, Yoichi Endo¹, Yusuke Miura¹, Toru Higuchi¹, Ken Kurosaki² (1. NFD, 2. Kyoto Univ.)

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

Oral presentation

[2C08-09] Fuel Technology Development

Thu. Sep 7, 2023 11:25 AM - 12:00 PM Room C (IB Bildg.1F IB015)

Chair:Keizo Matsuura(FUT)

11:25 AM - 11:40 AM

[2C08] Development of nuclear fuel fabrication technology using stereolithography and material extrusion

*Tomoomi Segawa¹, Masashi Watanabe¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Masato Kato¹ (1. JAEA)

11:40 AM - 11:55 AM

[2C09] Study on advanced LWR MOX fuel for effective Pu utilization and reduction of spent fuel assemblies

*Masayuki Naganuma¹, Yoshihisa Ikusawa¹, Yoshiyuki Shuji¹, Kiichi Suzuki¹ (1. JAEA)

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

Oral presentation

[2C10-15] Low Decontaminated Minor Actinide Bearing Mixed Oxide Fuels, Fast Reactor Recycle

Thu. Sep 7, 2023 2:45 PM - 4:20 PM Room C (IB Bildg.1F IB015)

Chair:Tsuyoshi Yaita(JAEA)

2:45 PM - 3:00 PM

[2C10] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(10) Fabrication of MA-bearing MOX fuel pellets

*Takashi Onishi¹, Kazuki Morishita¹, Masashi Watanabe¹, Keisuke Yokoyama¹, Masato Kato¹ (1. JAEA)

3:00 PM - 3:15 PM

[2C11] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(11) Evaluation of phase states and thermal properties of MA-bearing MOX fuels

*Keisuke Yokoyama¹, Masashi Watanabe¹, Takashi Onishi¹, Kazuki Morishita¹, Masato Kato¹ (1. JAEA)

3:15 PM - 3:30 PM

[2C12] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(12)Estimation of radial thermal conductivity of multilayer pellets prepared by 3D printer using 2 kinds of transient plane heat source method

*Kaito Kimura¹, Masayoshi Uno¹, Takashi Onitsuka¹ (1. Univ. of Fukui)

3:30 PM - 3:45 PM

[2C13] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(13)Measurement of Melting point of UO2 by local laser heating method

*Tatsumi Arima¹, Seina Urakawa¹, Yaohiro Inagaki¹, Masato Kato² (1. Kyushu university, 2. JAEA)

3:45 PM - 4:00 PM

[2C14] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(14)Melting point measurements of solid solutions of uranium oxide by containerless laser heating method

*SEINA URAKAWA¹, TATSUMI ARIMA¹, YAOHIRO INAGAKI¹, MASATO KATO² (1. Kyushu Univ., 2. JAEA)

4:00 PM - 4:15 PM

[2C15] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(15)Summary and future plan

*Shun Hirooka¹, Masato Kato¹, Masayoshi Uno², Tatsumi Arima³ (1. JAEA, 2. Univ. of Fukui, 3. Kyushu Univ.)

Time reserved for Chair （4:15 PM - 4:20 PM）

Oral presentation

[2C16-20] Accident Tolerant Fuel

Thu. Sep 7, 2023 4:20 PM - 5:40 PM Room C (IB Bildg.1F IB015)

Chair:Masato Kato(JAEA)

4:20 PM - 4:35 PM

[2C16] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1) Effect of coating on a safety evaluation and updated development road map

*Daiki Sato¹, Nozomu Murakami¹, Yuji Okada¹ (1. MHI)

4:35 PM - 4:50 PM

[2C17] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2) Effect of coating on a performance under normal operation

*Yuji Okada¹, Nozomu Murakami¹, Daiki Sato¹, Yasunari Shinohara², Koichi Ogata², Shimizu Yuki² (1. MHI, 2. NDC)

4:50 PM - 5:05 PM

[2C18] Material property evaluation of FeCrAl-ODS steel: The mechanical properties of neutron irradiated specimens

*Hiroki Yokoyama¹, Kan Sakamoto¹, Yusuke Miura¹, Nozue Mitsuo¹, Shinichiro Yamashita², Ikuo Ioka² (1. NFD, 2. JAEA)

5:05 PM - 5:20 PM

[2C19] Material property evaluation of FeCrAl-ODS steel: Fatigue property

*Chisato Sakaguchi¹, Kan Sakamoto¹, Yusuke Miura¹, Hideyuki Kasahara², Hajime Miyata², Junji Matsunaga³ (1. NFD, 2. HGNE, 3. GNF-J)

5:20 PM - 5:35 PM

[2C20] Development of Fuel Performance Code RANNS for Analysis of Accident Conditions

High Temperature Oxidation Behavior of Cr-coated Accident Tolerant Fuel Cladding

*Yoshinori Taniguchi¹, Yutaka Udagawa¹ (1. JAEA)

Time reserved for Chair （5:35 PM - 5:40 PM）

Oral presentation

[2C21-23] Excore Corrosion Behavior, Irradiation Behavior

Thu. Sep 7, 2023 5:40 PM - 6:30 PM Room C (IB Bildg.1F IB015)

Chair:Shun Hirooka(JAEA)

5:40 PM - 5:55 PM

[2C21] Corrosion behaviour of hydrogen absorbed M-MDA cladding

*YASUNARI SHINOHARA¹, Yuki Shimizu¹, Koichi Ogata¹, Yuji Okada², Daiki Sato² (1. NDC, 2. MHI)

5:55 PM - 6:10 PM

[2C22] Development of science-based MOX property model for irradiation behavior analysis code

*Takumi Oki¹, Masato Kato¹, Yoshihisa Ikusawa¹ (1. JAEA)

6:10 PM - 6:25 PM

[2C23] Irradiation behavior evaluation of Small Modular Reactor fuel at high burnup

*Keizo Matsuura¹, Yoshihiro Takagawa² (1. FUT, 2. Univ. of Fukui)

Time reserved for Chair （6:25 PM - 6:30 PM）

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2C01-07] Data Science, Fuel Research with Machine Learning

(1) General Introduction

(2)Design of machine learning models for highly accurate prediction of thermal conductivity

(3)Development of neural network potential of UO2

(4) Development of machine-learning gap conductance model

(5)Fabrication and Characterization of Metallic Uranium Compounds (UFe3B2, USiNi) Prepared via Spark Plasma Sintering

(6) Development of synchrotron radiation XRD measurement system for gas-floating melts

(7) Synthesis of Uranium Related Oxide to Verify Thermal Conductivity Predicted by Materials Informatics

[2C08-09] Fuel Technology Development

[2C10-15] Low Decontaminated Minor Actinide Bearing Mixed Oxide Fuels, Fast Reactor Recycle

(10) Fabrication of MA-bearing MOX fuel pellets

(11) Evaluation of phase states and thermal properties of MA-bearing MOX fuels

(12)Estimation of radial thermal conductivity of multilayer pellets prepared by 3D printer using 2 kinds of transient plane heat source method

(13)Measurement of Melting point of UO2 by local laser heating method

(14)Melting point measurements of solid solutions of uranium oxide by containerless laser heating method

(15)Summary and future plan

[2C16-20] Accident Tolerant Fuel

(1) Effect of coating on a safety evaluation and updated development road map

(2) Effect of coating on a performance under normal operation

High Temperature Oxidation Behavior of Cr-coated Accident Tolerant Fuel Cladding

[2C21-23] Excore Corrosion Behavior, Irradiation Behavior

Authentication

(3)Development of neural network potential of UO₂

(5)Fabrication and Characterization of Metallic Uranium Compounds (UFe₃B₂, USiNi) Prepared via Spark Plasma Sintering