Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2I08-17] SiC

Thu. Sep 14, 2017 2:45 PM - 5:25 PM Room I (C310 - C Block)

Chair:Hirotatsu Kishimoto (Muroran Inst. of Tech.)

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2:45 PM - 3:00 PM

[2I08] R&D for introducing silicon carbide materials to safety improvement of BWR's core

(1)Suppression of silica dissolution from SiC using corrosion resistant coating in simulated BWR environments

*Ryo Ishibashi¹, Takao Kondo¹, Shinichiro Yamashita² (1. Hitachi-GE Nuclear Energy, Ltd., 2. Japan Atomic Energy Agency)

3:00 PM - 3:15 PM

[2I09] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(2)Plant transient analysis with SiC clad fuel

*Yutaka Takeuchi¹, Kazuo Kakiuchi¹, Sato Hisaki¹, Noriko Shirasu², Hiroaki Saito², Shinichiro Yamashita² (1. Toshiba Corporation, 2. JAEA)

3:15 PM - 3:30 PM

[2I10] Severe accident analysis for core fuel with SiC cladding

(1)Evaluation by severe accident analysis code MAAP

*Hideki Horie¹, Yutaka Takeuchi¹, Fumie Sebe¹, Kenya Takiwaki¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. Toshiba Corporation)

3:30 PM - 3:45 PM

[2I11] Severe accident analysis for core fuel with SiC cladding

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM

*Kenya Takiwaki¹, Yutaka Takeuchi¹, Hideki Horie¹, Kazuo Kakiuchi¹, Hisaki Sato¹ (1. Toshiba Corporation)

3:45 PM - 4:00 PM

[2I12] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(1)Evaluations of influence on core neutronics characteristics

*Kazuya Yamaji¹, Kazuki Kirimura¹, Shinya Kosaka¹, Shinichiro Yamashita² (1. Mitsubishi Heavy Industries, Ltd., 2. Japan Atomic Energy Agency)

4:00 PM - 4:15 PM

[2I13] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(2)Study on fuel rod behavior during operation

*Kenichiro Furumoto¹, Hideyuki Teshima¹, Seiichi Watanabe¹, Teruhisa Yamamoto¹, Shinichiro Yamashita², Noriko Shirasu², Hiroaki Saito² (1. MNF, 2. JAEA)

4:15 PM - 4:30 PM

[2I14] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(3)Study on fuel behavior during design base accident

*Seiichi Watanabe¹, Hideyuki Teshima¹, Kenichiro Furumoto¹, Masaaki Katayama², Shinichiro Yamashita³ (1. MNF, 2. MHI, 3. JAEA)

4:30 PM - 4:45 PM

[2I15] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(4)Evaluations of severe accident tolerance for SiC

*Yoshinori Yamakoshi¹, Kazuki Kirimura¹, Shinya Kosaka¹, Shinichiro Yamashita² (1. Mitsubishi Heavy Industries, LTD., 2. Japan Atomic Energy Agency)

4:45 PM - 5:00 PM

[2I16] Microstructure and Strength Properties of Bonding Interface of NITE-SiC/SiC by Active Metal Brazing

*Atsuki Yoshihara¹, Naofumi nakazato¹, Joon-Soo Park², Chika Nogiwa¹, Hirotatsu Kishimoto¹ (1. Muroran Institute of Technology, 2. Organization of Advanced Sustainability Initiative for Energy System/Materials)

5:00 PM - 5:15 PM

[2I17] Role of irradiation defects in SiC on hydrothermal corrosion

*Sosuke Kondo¹, Yuki Maeda², Kazuhiro Fukami², Tatsuya Hinoki¹ (1. Institute of Advanced Energy, Kyoto University, 2. Department of Materials Science and Engineering, Kyoto University)

Time reserved for Chair (5:15 PM - 5:25 PM)

Session information

[2I08-17] SiC

[2I08] R&D for introducing silicon carbide materials to safety improvement of BWR's core

(1)Suppression of silica dissolution from SiC using corrosion resistant coating in simulated BWR environments

[2I09] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(2)Plant transient analysis with SiC clad fuel

[2I10] Severe accident analysis for core fuel with SiC cladding

(1)Evaluation by severe accident analysis code MAAP

[2I11] Severe accident analysis for core fuel with SiC cladding

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM

[2I12] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(1)Evaluations of influence on core neutronics characteristics

[2I13] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(2)Study on fuel rod behavior during operation

[2I14] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(3)Study on fuel behavior during design base accident

[2I15] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(4)Evaluations of severe accident tolerance for SiC

[2I16] Microstructure and Strength Properties of Bonding Interface of NITE-SiC/SiC by Active Metal Brazing

[2I17] Role of irradiation defects in SiC on hydrothermal corrosion

Authentication

Session information

[2I08-17] SiC

(1)Suppression of silica dissolution from SiC using corrosion resistant coating in simulated BWR environments

(2)Plant transient analysis with SiC clad fuel

(1)Evaluation by severe accident analysis code MAAP

(2)Evaluation by nuclear thermal hydraulics analysis code TRACTTM

(1)Evaluations of influence on core neutronics characteristics

(2)Study on fuel rod behavior during operation

(3)Study on fuel behavior during design base accident

(4)Evaluations of severe accident tolerance for SiC

Authentication

(2)Evaluation by nuclear thermal hydraulics analysis code TRACT^TM