Refine your search:     
Report No.
 - 
Search Results: Records 1-7 displayed on this page of 7
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Research and development roadmap for reactor physics 2017; Future of reactor physics projected by next generations

Yamamoto, Akio*; Chiba, Go*; Kirimura, Kazuki*; Miki, Yosuke*; Yokoyama, Kenji

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(4), p.241 - 245, 2018/04

no abstracts in English

Journal Articles

Technical basis of accident tolerant fuel updated under a Japanese R&D project

Yamashita, Shinichiro; Nagase, Fumihisa; Kurata, Masaki; Nozawa, Takashi; Watanabe, Seiichi*; Kirimura, Kazuki*; Kakiuchi, Kazuo*; Kondo, Takao*; Sakamoto, Kan*; Kusagaya, Kazuyuki*; et al.

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

In Japan, the research and development (R&D) project on accident tolerant fuel and other components (ATFs) of light water reactors (LWRs) has been initiated in 2015 for establishing technical basis of ATFs. The Japan Atomic Energy Agency (JAEA) has coordinated and carried out this ATF R&D project in cooperation with power plant providers, fuel venders and universities for making the best use of the experiences, knowledges in commercial uses of zirconium-base alloys (Zircaloy) in LWRs. ATF candidate materials under consideration in the project are FeCrAl steel strengthened by dispersion of fine oxide particles(FeCrAl-ODS) and silicon carbide (SiC) composite, and are expecting to endure severe accident conditions in the reactor core for a longer period of time than the Zircaloy while maintaining or improving fuel performance during normal operations. In this paper, the progresses of the R&D project are reported.

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

R&D for introducing advanced fuels contributing to safety improvement of current LWRs, 1; Overview of project

Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Shirasu, Noriko; Kurata, Masaki; Kaji, Yoshiyuki; Fukahori, Tokio; Watanabe, Seiichi*; Kirimura, Kazuki*; Kakiuchi, Kazuo*; et al.

no journal, , 

Since the accident at Fukushima Daiichi Nuclear Power Station, enhancing the accident tolerance of Light Water Reactors (LWRs) became a topic of serious discussion, and the research and development (R&D) for improving the safety LWRs has been activated in many countries. In Japan, the R&D project on accident tolerant fuel and other components (ATFs) of LWRs, which is sponsored and organized by the Ministry of Economy, Trade and Industry (METI), has been initiated in 2015 for establishing technical basis of ATFs. The Japan Atomic Energy Agency (JAEA) has coordinated and carried out this ATF R&D project in cooperation with power plant providers, fuel venders and universities for making the best use of the experiences, knowledges in commercial uses of zirconium-base alloys in LWRs.

Oral presentation

Oral presentation

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

Yamakoshi, Yoshinori*; Kirimura, Kazuki*; Kosaka, Shinya*; Yamashita, Shinichiro

no journal, , 

Accident tolerant of SiC under severe accident condition was evaluated on the assumption that SiC fuel cladding was implemented to existing PWR plant.

Oral presentation

The Feasibility study on SiC composite fuel cladding for the accident tolerant fuel to the existing PWR plants, 5; Evaluation of influence on core neutronics characteristics and fuel behavior

Murakami, Nozomu*; Kirimura, Kazuki*; Yamaji, Kazuya*; Sato, Daisuke*; Watanabe, Seiichi*; Sato, Daiki*; Furumoto, Kenichiro*; Yamashita, Shinichiro; Fukahori, Tokio

no journal, , 

The SiC/SiC composite has lower thermal conductivity than current Zry cladding, and it is necessary to raise a gap between the pellet and the cladding to prevent their contact from the viewpoint of pellet integrity. In the presentation, it will be reported that the effect of reduction of cladding diameter and hollow pellet on the temperature and the reactivity of the core.

7 (Records 1-7 displayed on this page)
  • 1