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Yamashita, Shinichiro
Nihon Genshiryoku Gakkai-Shi ATOMO
, 65(4), p.233 - 237, 2023/04
In the wake of the accident at the Fukushima Daiichi Nuclear Power Plant (NPP) of TEPCO due to the Great East Japan Earthquake in 2011, interest in the early implementation of accident tolerant fuel (ATF) not only for many existing NPPs but also for future NPPs, which is expected to dramatically improve the safety of light water reactors, has increased globally, and research and development is currently underway in many countries around the world. In this article, an overview of domestic ATF technology development that has been carried out with the support of the Ministry of Economy, Trade and Industry since 2015, will be introduced.
Sato, Hiroyuki; Ohashi, Hirofumi; Nakagawa, Shigeaki
Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 8 Pages, 2016/06
This paper intends to propose a practical solution to protect HTGR from severe oxidation against air ingress accidents without reliance on subsystems. Firstly, a change is made to the center reflector structure to minimize temperature difference during the accident condition in order to reduce buoyancy-driven natural circulation in the reactor. Secondly, a modified structure of the upper reflector is suggested to prevent massive air ingress against a rupture in standpipes. As a preliminary study, a numerical analysis is performed for a typical prismatic-type HTGR to study the effectiveness of the proposed design concept using simplified lumped element models. The results showed that amount of air ingress into the reactor can be significantly reduced with practical changes to local structure in the reactor.
Tsutani, Sadahiro*; Takeshita, Hiroshi*; Edajima, Toshikazu*; Motooka, Masafumi*
PNC TJ8224 93-001, 128 Pages, 1993/06
no abstracts in English
Tsujino, Takeshi; Takeshita, Isao; ; Nomura, Masayuki;
Proc. of the 8th Pacific Basin Nuclear Conf., p.9-E-1 - 9-E-6, 1992/00
no abstracts in English
Asahi, Yoshiro; ;
Nuclear Science and Engineering, 96, p.73 - 84, 1987/00
Times Cited Count：3 Percentile：51.52(Nuclear Science & Technology)no abstracts in English
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.
Sato, Daiki*; Watanabe, Seiichi*; Komiyama, Daisuke*; Furumoto, Kenichiro*; Okamoto, Michiaki*; Yamato, Masaaki*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
It is expected that SiC cladding tube has high corrosion resistance and high strength under LOCA condition in existing PWR. There is little data for SiC cladding tube in the high temperature environment. So the apparatus which was capable of testing at LOCA simulated condition was manufactured for SiC cladding tube. The modified LOCA test was carried out for investigating the behavior of SiC cladding tube.
Suzuki, Hiroaki*; Morita, Yoshihiro*; Naito, Masanori*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki
no journal, ,
Severe accident code SAMPSON was upgraded by introducing the models of Zr oxidation in air, and spray cooling, etc, in this study. Analytical results on spent fuel pool (SFP) accident were obtained and effectiveness of the spray cooling system for the safety measure of the SFP was discussed in this study.
Maeda, Shigetaka; Itagaki, Wataru; Maeda, Koji; Maki, Ryosuke*; Yoshida, Katsumi*
no journal, ,
Highly microstructure-controlled ceramic neutron absorbers were developed for improving safety of fast reactors. The control rod worth was evaluated using several compositions as parameter. It was confirmed that the effect of additives on control rod worth was negligible.
Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Kurata, Masaki; Kawanishi, Tomohiro; Kaji, Yoshiyuki; Fukahori, Tokio; Watanabe, Seiichi*; Murakami, Nozomu*; Sato, Hisaki*; et al.
no journal, ,
In Japan, research and development (R&D) program for establishing technical basis of ATF started in 2015 and is being conducted in cooperation with power plant providers, fuel venders and universities for making the most use of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial LWRs. The present paper reviews the progress of the development and summarizes subjects to be solved for ATF cladding, based on the attribute guide which was originally drawn up in the Japanese ATF R&D program as it should be an indicator of proper ATF development guidance.
Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Shirasu, Noriko; Kurata, Masaki; Kaji, Yoshiyuki; Fukahori, Tokio; Watanabe, Seiichi*; Murakami, Nozomu*; Sato, Hisaki*; 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 for improving the safety LWRs has been activated in many countries. This project is one of the projects that entrusted from the Ministry of Economy, Trade and Industry Agency for Natural Resources and Energy. Using a domestic human source, an analysis tool, know-how and experience, the basic technique to apply an accident tolerant fuel material to an existing LWRs is developed in the project. It is started from October, 2015 and is carrying out this project continuously.
Sakamoto, Kan*; Ukai, Shigeharu*; Kimura, Akihiko*; Yamaji, Akifumi*; Kusagaya, Kazuyuki*; Kondo, Takao*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
Using the acquired material data by 2016, the feasibility of the reactor core, accident progress relaxation effect at an accident and a severe accident were confirmed by various analysis when Zircaloy replaced to FeCrAl-ODS steel. The results including the post irradiation examination in fiscal year 2017 will be introduced by this presentation.
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.
Watanabe, Seiichi*; Sato, Daiki*; Furumoto, Kenichiro*; Murakami, Nozomu*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
SiC composite material is one of the candidate material as the accident tolerant fuel. The acquisition of the irradiation properties, the evaluation of fuel design and accident safety are main problems for the SiC composite material. For the solution, out- and in-pile testings of SiC composite, development of evaluation technique of fuel behavior, core characteristic and the safety at accident, analyses and evaluations by using the developed techniques have been carried out.
Kaji, Yoshiyuki; Nemoto, Yoshiyuki; Nagatake, Taku; Yoshida, Hiroyuki; Tojo, Masayuki*; Goto, Daisuke*; Nishimura, Satoshi*; Suzuki, Hiroaki*; Yamato, Masaaki*
no journal, ,
The objectives of this study is to enhance the analytical method and safety of spent fuel pool under severe accident conditions. In this presentation, we explain about general view of results of this project.
Yamashita, Shinichiro; Mohamad, A. B.; Soma, Yasutaka; Nemoto, Yoshiyuki; Ioka, Ikuo; Kaji, Yoshiyuki; Osaka, Masahiko
no journal, ,
Japan's Accident Tolerant Fuel (ATF) research and development (R&D) program has been conducted since 2015 in cooperation with power plant providers, fuel venders and universities for making the most use of the experiences in R&D, practical design, and evaluations of fuels and cores of commercial Light Water Reactors (LWRs). An overview of the present R&D progress is given, including the role of Japan Atomic Energy Agency (JAEA) in the program.
