Oral presentation

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

[1I13-17] characteristics of fuel cladding

Mon. Mar 27, 2017 4:25 PM - 5:50 PM Room I (16-304 Building No.16)

Chair: Ken Kurosaki (Osaka Univ.)

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4:25 PM - 4:40 PM

[1I13] The evaluation on the applicability of SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(1)Evaluations of the fuel rod behavior during PWR operational conditions

*Kenichiro Furumoto¹, Seiichi Watanabe¹, Teruhisa Yamamoto¹, Hideyuki Teshima¹, Shinichiro Yamashita², Fumihisa Nagase² (1. MNF, 2. JAEA)

4:40 PM - 4:55 PM

[1I14] The evaluation on the applicability of SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(2)Evaluations of severe accident tolerance for SiC

*Yoshinori Yamakoshi¹, Manabu Miyata¹, Kazuki Kirimura¹, Masatsugu Mizokami¹, Shinya Kosaka¹, Shinichiro Yamashita², Fumihisa Nagase² (1. Mitsubishi Heavy Industries, ltd., 2. Japan Atomic Energy Agency)

4:55 PM - 5:10 PM

[1I15] The high temperature strength anisotropy of full and/or partial-recrystallized Zr-Nb alloy

*Sho Kano¹, Huilong Yang¹, Nagasaka Takuya², Hiroaki Abe¹ (1. The University of Tokyo, 2. National Institute for Fusion Science)

5:10 PM - 5:25 PM

[1I16] The development of self-healing coating on zirconium alloy

*Zhengang Duan¹, Huilong Yang², Sho Kano², Kenta Murakami², Hiroaki Abe² (1. Tohoku University, 2. The University of Tokyo)

5:25 PM - 5:40 PM

[1I17] The Relationship between the Circumferential Strain and the Bending Strength after Quench of the Fuel Cladding Ballooned during a LOCA

*Takanori YUMURA¹, Masaki AMAYA¹ (1. JAEA)

Time reserved for Chair (5:40 PM - 5:50 PM)

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