Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Sakamoto, Kan*; Miura, Yusuke*; Ukai, Shigeharu; Ono, Naoko*; Kimura, Akihiko*; Yamaji, Akifumi*; Kusagaya, Kazuyuki*; Takano, Sho*; Kondo, Takao*; Ikegawa, Tomohiko*; et al.
Journal of Nuclear Materials, 557, p.153276_1 - 153276_11, 2021/12
Times Cited Count：73 Percentile：99.17(Materials Science, Multidisciplinary)A FeCrAl-oxide dispersion strengthened (ODS) alloy is a promising candidate alloy for the accident tolerant fuel (ATF) cladding of light water reactors (LWRs) and being developed in Japan recently. This paper will introduce the progress of development of accident tolerant FeCrAl-ODS fuel claddings for boiling water reactors (BWRs) in Japan. Both the experimental and the analytical studies have been performed to evaluate the influence of implementation of the FeCrAl-ODS fuel claddings to the current BWRs. The experimental studies have been conducted to obtain and accumulate key material properties of FeCrAl-ODS fuel claddings by using bar, sheet and tube-shaped materials to support the evaluations in the analytical studies. At the end of paper, the challenges and prospects found in the program are highlighted to enhance international collaborations to accelerate the development of FeCrAl-ODS fuel cladding.
Ikegawa, Tomohiko*; Ishibashi, Ryo*; Sakamoto, Kan*; Hirai, Mutsumi*; Yamashita, Shinichiro
no journal, ,
no abstracts in English
Sato, Hisaki*; Kakiuchi, Kazuo*; Ishibashi, Ryo*; Ikegawa, Tomohiko*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
SiC composite materials applied to a cladding tube and a channel box for BWR have been developed for introduction of the accident tolerant fuel to an existing LWRs. The outline of the outcome in fiscal year 2017 will be introduced by this presentation.
Ikegawa, Tomohiko*; Ishibashi, Ryo*; Sakamoto, Kan*; Yamashita, Shinichiro
no journal, ,
Zircaloy (Zry) is used in LWRs generally. When steam and Zry reacted under the high temperature environment, hydrogen and heat of reaction generated. Those have an influence on a presence of core damage at an accident. The effect of the accident tolerant fuel was quantitatively investigated in the study when the accident management (depressurization of RPV and water pouring by firefighting car) was carried out in the severe accident.
Ishibashi, Ryo*; Ikegawa, Tomohiko*; Tanabe, Shigetada*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
For the purpose of improving corrosion resistance of silicon carbide (SiC) in boiling water reactor (BWR) environments, corrosion resistant coatings to SiC substrate were evaluated. Due to its lower hydrogen generation rate and lower reaction heat in comparison with a conventional zircaloy, SiC is expected to be a proper material for accident tolerant fuel. On the other hand, there are still a lot of critical issues left for the practical application of SiC fuel cladding and fuel channel box, one of which is hydrothermal corrosion. In this study, corrosion behavior of candidate coatings to SiC substrate and joint portion were evaluated in unirradiated high purity water environments.
Ishibashi, Ryo*; Hirosaka, Kazuma*; Ikegawa, Tomohiko*; Shibata, Masatoshi*; Sasaki, Masana*; Tsuchiya, Akiyuki*; Pham, V. H.; Kurata, Masaki; Nemoto, Yoshiyuki
no journal, ,
no abstracts in English
