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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.
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).
Hidaka, Akihide; Nakano, Yoshihiro; Watanabe, Yoko; Arai, Nobuyoshi; Sawada, Makoto; Kanaizuka, Seiichi*; Katogi, Aki; Shimada, Mayuka*; Ishikawa, Tomomi*; Ebine, Masako*; et al.
JAEA-Review 2016-011, 208 Pages, 2016/07
JAEA-Review-2016-011-01.pdf:33.85MBJAEA-Review-2016-011-02.pdf:27.68MB
JAEA has been conducting the Instructor Training Program (ITP) since 1996 under the auspices of MEXT to contribute to human resource development in currently 11 Asian countries in the field of radiation utilization for seeking peaceful use of nuclear energy. ITP consists of Instructor Training Course (ITC), Follow-up Training Course (FTC) and Nuclear Technology Seminars. In the ITP, trainings or seminars relating to technology for nuclear utilization are held in Japan by inviting nuclear related people from Asian countries to Japan and after that, the past trainees are supported during FTC by dispatching Japanese specialists to Asian countries. News Letter is also prepared to provide the broad range of information obtained through the trainings for local people near NPPs in Japan. The present report describes the activities of FY2014 ITP and future challenges for improving ITP more effectively.
Watanabe, Yoko; Arai, Nobuyoshi; Sawada, Makoto; Kanaizuka, Seiichi; Shimada, Mayuka*; Ishikawa, Tomomi*; Nakamura, Kazuyuki
JAEA-Review 2015-026, 38 Pages, 2015/11
JAEA-Review-2015-026.pdf:10.55MB
JAEA has conducted Nuclear Technology Seminar for Asian countries which plan to introduce NPP, in order to increase the number of engineers and specialists. The Nuclear Technology Seminar on the Basic Radiation Knowledge for School Education Course was launched in 2012 due to increased recognition of the dissemination of the basic knowledge of radiation in public and education sectors as an important issue in the aftermath of the Fukushima Dai-ichi NPP Accident. In response to the requests of past participants, a new exercise "Joint experiment with high school students" was introduced from 2014 to provide an international learning experience for the course participants and the local Japanese students. A new learning material was also developed to help participants to study the basics of radiation in English. All the course activities including the details of preparatory process and course evaluation were described in this report.
Nakamura, Kazuyuki; Arai, Nobuyoshi; Kanaizuka, Seiichi; Sakurai, Takeshi; Sawai, Tomotsugu; Sawada, Makoto; Nakagawa, Norio; Murakami, Hiroyuki; Yabuuchi, Yukiko; Yamashita, Kiyonobu; et al.
no journal, ,
JAEA is performing the human resource development for eleven Asian countries as contract with MEXT. Problems and their response to this works will be reported.
Teshima, Hideyuki*; Watanabe, Seiichi*; Furumoto, Kenichiro*; Kirimura, Kazuki*; Yamakoshi, Yoshinori*; Ioka, Ikuo; Yamashita, Shinichiro; Kaji, Yoshiyuki
no journal, ,
no abstracts in English
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.
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.
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.
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.
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.
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.
Furumoto, Kenichiro*; Sato, Daiki*; Watanabe, Seiichi*; Yamashita, Shinichiro; Fukahori, Tokio
no journal, ,
The stress of SiC cladding to the existing PWR is important to evaluate the integrity of SiC cladding. It is necessary to comprehend mechanical properties of each of longitudinal and circumferential direction because there is anisotropy in mechanical properties of SiC cladding. The A-EDC test which was the circumferential direction mechanical test developed in recent years. The mechanical properties of SiC cladding in circumferential direction was measured using the A-EDC.
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.
Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Kaji, Yoshiyuki; Fukahori, Tokio; Nozawa, Takashi*; Watanabe, Seiichi*; Murakami, Nozomu*; Sato, Hisaki*; et al.
no journal, ,
Yamashita, Shinichiro; Ioka, Ikuo; Nemoto, Yoshiyuki; Kawanishi, Tomohiro; Kaji, Yoshiyuki; Fukahori, Tokio; Nozawa, Takashi*; Watanabe, Seiichi*; Murakami, Nozomu*; Sato, Hisaki*; et al.
no journal, ,
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.
