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Journal Articles

The Applicability of SiC-SiC fuel cladding to conventional PWR power plant

Furumoto, Kenichiro*; Watanabe, Seiichi*; Yamamoto, Teruhisa*; Teshima, Hideyuki*; Yamashita, Shinichiro; Saito, Hiroaki; Shirasu, Noriko

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10 Pages, 2017/09

Since 2015, Mitsubishi Nuclear Fuel (MNF) has joined in a Japanese R&D project of ATF founded by the Ministry of Economy, Trade and Industry (METI) as a subcontractor to Japan Atomic Energy Agency (JAEA) which is the prime contractor to METI. In this program, MNF plans to evaluate an influence of Silicon Carbide (SiC) composite cladding upon fuel rod behavior in current pressurized water reactors (PWR). This paper reports the evaluation result of the applicability of fuel rod with SiC composite cladding for a conventional PWR. For the applicability evaluations of SiC composite to conventional PWR, both of analytical evaluations and out-of-pile tests for SiC composite were conducted. Analytical evaluations were performed by Mitsubishi's own fuel rod design code and the fuel rod behavior evaluation code developed by JAEA. These codes were modified to evaluate the behavior of the fuel rod with SiC composite cladding. As out-of-pile tests, thermal diffusivity measurement and autoclave corrosion test for SiC composite samples were performed. Test apparatus were developed for evaluation of performance of SiC composite under the condition simulated design basis accident (DBA).

Oral presentation

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 4; SiC composite material for PWR

Teshima, Hideyuki*; Watanabe, Seiichi*; Furumoto, Kenichiro*; Kirimura, Kazuki*; Yamakoshi, Yoshinori*; Ioka, Ikuo; Yamashita, Shinichiro; Kaji, Yoshiyuki

no journal, , 

no abstracts in English

Oral presentation

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

Furumoto, Kenichiro*; Teshima, Hideyuki*; Watanabe, Seiichi*; Yamamoto, Teruhisa*; Shirasu, Noriko; Saito, Hiroaki; Yamashita, Shinichiro

no journal, , 

Mitsubishi Nuclear Fuel (MNF) plans to evaluate an influence of Silicon Carbide (SiC) composite cladding upon fuel rod behavior in current pressurized water reactors (PWR). In this presentation, the evaluation result of the applicability of fuel rod with SiC composite cladding for a conventional PWR will be reported. For the applicability evaluations of SiC composite to conventional PWR, both of analytical evaluations and out-of-pile tests for SiC composite were conducted. Analytical evaluations were performed by Mitsubishi's own fuel rod design code and the fuel rod behavior evaluation code developed by JAEA. These codes were modified to evaluate the behavior of the fuel rod with SiC composite cladding.

Oral presentation

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

Watanabe, Seiichi*; Teshima, Hideyuki*; Furumoto, Kenichiro*; Katayama, Masaaki*; Yamashita, Shinichiro

no journal, , 

Due to its hydrogen-generation rate and reaction heat being lower than those of conventional Zircaloy, SiC is expected to be an appropriate material for accident-tolerant fuels. There are, however, only a few knowledge on behavior of SiC composite cladding under design basis accident condition (DBA). In this study test apparatus were developed for evaluation of behavior of SiC composite cladding and the mock-up tests using SiC cladding were performed under the condition simulated DBA.

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