Oral presentation

[1I07-12] FP behavior

Mon. Mar 27, 2017 2:45 PM - 4:25 PM Room I (16-304 Building No.16)

Chair: Hiroyuki Serizawa (JAEA)

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2:45 PM - 3:00 PM

[1I07] Fundamental Research on Fission Product Chemistry

(1)Development and basic performance of the reproductive test facility of fission product release and transport

*Naoya Miyahara¹, Shuhei Miwa¹, Juntaro Takada¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[1I08] Fundamental Research on Fission Product Chemistry

(2)The atmospheric effect on the Cs deposition behaviors onto stainless steels

*Kunihisa Nakajima¹, Eriko Suzuki¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

3:15 PM - 3:30 PM

[1I09] Fundamental Research on Fission Product Chemistry

(3)Effect of atmosphere on the vaporization behavior of CsFeSiO₄

*Eriko Suzuki¹, Kunihisa Nakajima¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[1I10] Fundamental Research on Fission Product Chemistry

(4)Chemical state of adsorbed Cesium under LWR severe accident studied by hard X-ray photoelectron spectroscopy

*Masaaki Kobata¹, Tetsuo Okane¹, Keisuke Kobayashi¹, Kenji Ohwada², Kunihisa Nakajima¹, Eriko Suzuki¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency, 2. National Institutes for Quantum and Radiological Science and Technology)

3:45 PM - 4:00 PM

[1I11] Fundamental Research on Fission Product Chemistry

(5)On the release and transportation behavior of Strontium under an LWR severe accident

Shuhei Miwa¹, Naoya Miyahara¹, Eriko Suzuki¹, Kunihisa Nakajima¹, *Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

4:00 PM - 4:15 PM

[1I12] Behavior characterization of volatile fission products in meltdown nuclear fuels by a method in consideration of surface and interface effects

Wettability of cesium halide on solid surface of yttria-stabilized zirconia

*Hiroto Ishii¹, Ken Kurosaki^1,2, Yukihiro Murakami³, Yuji Ohishi¹, Hiroaki Muta¹, Masayoshi Uno³, Shinsuke Yamanaka^1,3 (1. Osaka University , 2. JST PRESTO, 3. University of Fukui)

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

Oral presentation

[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）

Sessions

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

[1I07-12] FP behavior

[1I07] Fundamental Research on Fission Product Chemistry

(1)Development and basic performance of the reproductive test facility of fission product release and transport

[1I08] Fundamental Research on Fission Product Chemistry

(2)The atmospheric effect on the Cs deposition behaviors onto stainless steels

[1I09] Fundamental Research on Fission Product Chemistry

(3)Effect of atmosphere on the vaporization behavior of CsFeSiO₄

[1I10] Fundamental Research on Fission Product Chemistry

(4)Chemical state of adsorbed Cesium under LWR severe accident studied by hard X-ray photoelectron spectroscopy

[1I11] Fundamental Research on Fission Product Chemistry

(5)On the release and transportation behavior of Strontium under an LWR severe accident

[1I12] Behavior characterization of volatile fission products in meltdown nuclear fuels by a method in consideration of surface and interface effects

Wettability of cesium halide on solid surface of yttria-stabilized zirconia

[1I13-17] characteristics of fuel cladding

[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

[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

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

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

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

Authentication

Sessions

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

[1I07-12] FP behavior

(1)Development and basic performance of the reproductive test facility of fission product release and transport

(2)The atmospheric effect on the Cs deposition behaviors onto stainless steels

(3)Effect of atmosphere on the vaporization behavior of CsFeSiO4

(4)Chemical state of adsorbed Cesium under LWR severe accident studied by hard X-ray photoelectron spectroscopy

(5)On the release and transportation behavior of Strontium under an LWR severe accident

Wettability of cesium halide on solid surface of yttria-stabilized zirconia

[1I13-17] characteristics of fuel cladding

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

(2)Evaluations of severe accident tolerance for SiC

Authentication

(3)Effect of atmosphere on the vaporization behavior of CsFeSiO₄