Oral presentation

[3D01-05] MOX Fuels for Fast Reactor

Wed. Mar 28, 2018 9:30 AM - 10:55 AM Room D (R1-212 -R1 Building)

Chair: Shuhei Miwa (JAEA)

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9:30 AM - 9:45 AM

[3D01] Science-based Integrated Models for MOX Properties

(1)Relation among lattice constant, coefficient of thermal expansion, mechanical properties and heat capacity

*Shun Hirooka¹, Masato Kato¹, Masatoshi Akashi¹, Kyoichi Morimoto¹, Taku Matsumoto¹ (1. Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[3D02] Science-based Integrated Models for MOX Properties

(2)Relation among oxygen potential, oxygen diffusion coefficient and vapor pressure

*Masashi Watanabe¹, Taku Matsumoto¹, Shun Hirooka¹, Masato Kato¹ (1. Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[3D03] Science-based Integrated Models for MOX Properties

(3)Heat capacity and thermal conductivity

*Masato Kato¹, Kyoichi Morimoto¹, Hiroki Nakamura¹, Masahiko Machida¹ (1. Japan Atomic Energy Agency)

10:15 AM - 10:30 AM

[3D04] Irradiation Behavior of Fast Reactor Fuel Pins

(1)Evaluation of Cesium Behavior by Coupled Computer Code System

*Tomoyuki Uwaba¹, Keisuke Yokoyama¹, Yoshihisa Ikusawa¹, Junich Nemoto¹, Ikuo Ishitani¹, Masahiro Ito¹ (1. Japan Atomic Energy Agency)

10:30 AM - 10:45 AM

[3D05] Irradiation Behavior of Fast Reactor Fuel Pins

(2)Irradiation Behavior of Annular Pellet Pins

*Keisuke Yokoyama¹, Tomoyuki Uwaba¹, Takashi Tanno¹, Hiroshi Oka¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[3D06-09] Fundamental Properties of Fuels and FPs

Wed. Mar 28, 2018 10:55 AM - 12:00 PM Room D (R1-212 -R1 Building)

Chair: Masashi Watanabe (JAEA)

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10:55 AM - 11:10 AM

[3D06] Prediction of decay heat of fuel debris considering volatilization of fission products

*Keisuke Okumura¹, Eka Sapta Riyana¹, Wakaei Sato², Hirobumi Maeda², Manabu Fujita³ (1. JAEA, 2. NESI, 3. JPC)

11:10 AM - 11:25 AM

[3D07] Microstructure development in YSZ induced by high density electronic excitation

*Yoshiaki Yamaguchi¹, Tomokazu Yamamoto¹, Satoru Yoshioka¹, Kazuhiro Yasuda¹, Syo Matsumura¹, Seiya Takaki², Norito Ishikawa² (1. Kyushu Univ., 2. JAEA)

11:25 AM - 11:40 AM

[3D08] Behavior Characterization of Volatile Fission Products in Meltdown Nuclear Fuels by a Method in Consideration of Surface and Interface Effects

(6)Wettability of Liquid Caesium Halides on Oxide Single Crystals

*Hiroto Ishii¹, Yuji Ohishi¹, Hiroaki Muta¹, Masayoshi Uno², Shinsuke Yamanaka¹, Ken Kurosaki^3,2,1 (1. Osaka University , 2. Research Institute of Nuclear Engineering, University of Fukui, 3. JST PRESTO)

11:40 AM - 11:55 AM

[3D09] Hydrogenation Behavior of Zircaloy and Hafnium during Corrosion

*Kazuhiro Tsuchida¹, Thi Mai Dung Do¹, Kenta Murakami¹, Masahide Suzuki¹, Akihiro Iwase² (1. Nagaoka University of Technology, 2. Osaka Prefecture University)

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

Oral presentation

[3D10-13] Fuel Cladding

Wed. Mar 28, 2018 2:45 PM - 3:55 PM Room D (R1-212 -R1 Building)

Chair: Masayoshi Uno (Univ. of Fukui)

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2:45 PM - 3:00 PM

[3D10] Development of Corrosion Resistant Coating Technology to Silicon Carbide Fuel Materials
(2)

*Ryo Ishibashi¹, Kazushige Ishida¹, Katsumasa Miyazaki¹, Takao Kondou² (1. Hitachi,Ltd., 2. Hitachi-GE Nuclear Energy, Ltd.)

3:00 PM - 3:15 PM

[3D11] The development of self-healing coating on zirconium alloy for light water reactors

*Zhengang Duan¹, Huilong Yang², Sho Kano², Jingjie Shen², Zishou Zhao², John McGrady², Hiroaki Abe² (1. Tohoku University, 2. The University of Tokyo)

3:15 PM - 3:30 PM

[3D12] Correlation between Fe distribution and irradiation defects in irradiated zirconium alloys

*Takashi Sawabe¹, Takeshi Sonoda¹ (1. CRIEPI)

3:30 PM - 3:45 PM

[3D13] Evaluation of Mechanical Property of High Burnup BWR Fuel Cladding by Internal Pressurization Burst Test

*Akihiro Yamauchi¹, Keizo Ogata¹ (1. Regulatory Standard and Research Department Secretariat of Nuclear Regulation Authority)

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

Sessions

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[3D01-05] MOX Fuels for Fast Reactor

[3D01] Science-based Integrated Models for MOX Properties

(1)Relation among lattice constant, coefficient of thermal expansion, mechanical properties and heat capacity

[3D02] Science-based Integrated Models for MOX Properties

(2)Relation among oxygen potential, oxygen diffusion coefficient and vapor pressure

[3D03] Science-based Integrated Models for MOX Properties

(3)Heat capacity and thermal conductivity

[3D04] Irradiation Behavior of Fast Reactor Fuel Pins

(1)Evaluation of Cesium Behavior by Coupled Computer Code System

[3D05] Irradiation Behavior of Fast Reactor Fuel Pins

(2)Irradiation Behavior of Annular Pellet Pins

[3D06-09] Fundamental Properties of Fuels and FPs

[3D06] Prediction of decay heat of fuel debris considering volatilization of fission products

[3D07] Microstructure development in YSZ induced by high density electronic excitation

[3D08] Behavior Characterization of Volatile Fission Products in Meltdown Nuclear Fuels by a Method in Consideration of Surface and Interface Effects

(6)Wettability of Liquid Caesium Halides on Oxide Single Crystals

[3D09] Hydrogenation Behavior of Zircaloy and Hafnium during Corrosion

[3D10-13] Fuel Cladding

[3D10] Development of Corrosion Resistant Coating Technology to Silicon Carbide Fuel Materials
(2)

[3D11] The development of self-healing coating on zirconium alloy for light water reactors

[3D12] Correlation between Fe distribution and irradiation defects in irradiated zirconium alloys

[3D13] Evaluation of Mechanical Property of High Burnup BWR Fuel Cladding by Internal Pressurization Burst Test

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