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Minato, Kazuo; Ogawa, Toru
Comprehensive Nuclear Materials, 2nd Edition, Vol.5, p.334 - 360, 2020/08
TRISO coated particle fuel has been developed for the high temperature gas-cooled reactors, which consists of microspherical fuel kernel and coating layers of pyrolytic carbon and silicon carbide. To improve the high temperature stability, the resistance to the chemical attack by fission products and the retention of fission products of the TRISO coated particle fuels, several types of advanced fuels were proposed and tested. Coated particle fuels for fast reactors were also proposed and tested. In this paper, fuel designs, fabrications, characterization techniques and fuel performance of these advanced coated particle fuels are systematically described. This is the updated version of the paper having the same title in Comprehensive Nuclear Materials published in 2012.
Ueta, Shohei; Mizuta, Naoki; Fukaya, Yuji; Goto, Minoru; Tachibana, Yukio; Honda, Masaki*; Saiki, Yohei*; Takahashi, Masashi*; Ohira, Koichi*; Nakano, Masaaki*; et al.
Nuclear Engineering and Design, 357, p.110419_1 - 110419_10, 2020/02
Times Cited Count：1 Percentile：11.8(Nuclear Science & Technology)The concept of a plutonium (Pu) burner HTGR is proposed to incarnate highly-effective Pu utilization by its inherent safety features. The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO
) and yttria stabilized zirconia (YSZ) as an inert matrix. This paper presents feasibility study of Pu burner HTGR and R&D on the 3S-TRISO fuel.
Ueta, Shohei; Aihara, Jun; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*
Mechanical Engineering Journal (Internet), 5(5), p.18-00084_1 - 18-00084_9, 2018/10
To develop the security and safety fuel (3S-TRISO fuel) for Pu-burner high temperature gas-cooled reactor (HTGR), R&D on zirconium carbide (ZrC) directly coated on yttria stabilized zirconia (YSZ) has been started in the Japanese fiscal year 2015. As results of the direct coating test of ZrC on the dummy YSZ particle, ZrC layers with 18 - 21 microns of thicknesses have been obtained with 0.1 kg of particle loading weight. No deterioration of YSZ exposed by source gases of ZrC bromide process was observed by Scanning Transmission Electron Microscope (STEM).
Ueta, Shohei; Aihara, Jun; Mizuta, Naoki; Goto, Minoru; Fukaya, Yuji; Tachibana, Yukio; Okamoto, Koji*
Proceedings of 9th International Topical Meeting on High Temperature Reactor Technology (HTR 2018) (USB Flash Drive), 7 Pages, 2018/10
The security and safety fuel (3S-TRISO fuel) employs the coated fuel particle with a fuel kernel made of plutonium dioxide (PuO) and yttria stabilized zirconia (YSZ) as an inert matrix. Especially, a zirconium carbide (ZrC) coating is one of key technologies of the 3S-TRISO, which performs as an oxygen getter to reduce the fuel failure due to internal pressure during the irradiation. R&Ds on ZrC coating directly on the dummy CeO-YSZ kernel have been carried in the Japanese fiscal year 2017. As results of ZrC coating tests by the bromide chemical vapor deposition process, stoichiometric ZrC coatings with 3 - 18 microns of thicknesses were obtained with 0.1 kg of particle loading weight.
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.
Ueta, Shohei; Aihara, Jun; Goto, Minoru; Tachibana, Yukio; Okamoto, Koji*
Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 4 Pages, 2017/07
To develop the security and safety fuel (3S-TRISO fuel) for Pu-burner high temperature gas-cooled reactor (HTGR), R&D on zirconium carbide (ZrC) directly coated on yttria stabilized zirconia (YSZ) has been started in the Japanese fiscal year 2015. As results of the direct coating test of ZrC on the dummy YSZ particle, ZrC layers with 18 - 21 microns of thicknesses have been obtained with 0.1 kg of particle loading weight. No deterioration of YSZ exposed by source gases of ZrC bromide process was observed by Scanning Transmission Electron Microscope (STEM).
Iwai, Takashi; Nakajima, Kunihisa; Kikuchi, Hironobu; Nagashima, Hisao; Kimura, Yasuhiko; Matsui, Hiroki; Arai, Yasuo
JAERI-Research 2002-038, 69 Pages, 2003/01
JAERI-Research-2002-038.pdf:12.46MB
Uranium-plutonium mixed carbide and nitiride fuel pins were fabricated in JAERI and irradiated at fast test rector JOYO based on the JAERI-JNC joint research program. The results of non-destructive and destructive post irradiation examinations cariied out at JNC were reported elsewhere. This report summarizes the results of destructive post irradiation examinations of (U,Pu)C and (U,Pu)N fuel pins carried out at JAERI.
Arai, Yasuo; Iwai, Takashi; Nakajima, Kunihisa; Nagashima, Hisao; Nihei, Yasuo; Katsuyama, Kozo*; Inoue, Masaki*
Proceedings of GLOBAL2003 Atoms for Prosperity; Updating Eisenhower's Global Vision for Nuclear Energy (CD-ROM), p.1686 - 1693, 2003/00
no abstracts in English
Ueta, Shohei; Tobita, Tsutomu*; Ino, Hiroichi*; Takahashi, Masashi*; Sawa, Kazuhiro
JAERI-Tech 2002-085, 41 Pages, 2002/11
JAERI-Tech-2002-085.pdf:2.66MB
no abstracts in English
Minato, Kazuo; Fukuda, Kosaku; Ishikawa, Akiyoshi; Mita, Naoaki
Journal of Nuclear Materials, 246(2-3), p.215 - 222, 1997/00
Times Cited Count：16 Percentile：75.78(Materials Science, Multidisciplinary)no abstracts in English
Tobita, Tsutomu; Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kosaku; Sekino, Hajime; Iida, Shozo;
JAERI-Research 96-014, 34 Pages, 1996/03
JAERI-Research-96-014.pdf:2.15MB
no abstracts in English
Minato, Kazuo; ; Sawa, Kazuhiro; Tobita, Tsutomu; Fukuda, Kosaku
JAERI-Tech 95-056, 45 Pages, 1996/01
no abstracts in English
W.S.Charlton*; T.A.Parish*; S.Raman*; Shinohara, Nobuo; Ando, Masaki
PHYSOR 96: Int. Conf. on the Physics of Reactors, 3, p.F11 - F20, 1996/00
no abstracts in English
Minato, Kazuo; ; Fukuda, Kosaku; *; *; *; *
Nuclear Technology, 111, p.260 - 269, 1995/08
Times Cited Count：4 Percentile：43.23(Nuclear Science & Technology)no abstracts in English
Minato, Kazuo; Ogawa, Toru; Fukuda, Kosaku
JAERI-Review 95-004, 26 Pages, 1995/03
JAERI-Review-95-004.pdf:0.95MB
no abstracts in English
Minato, Kazuo; Fukuda, Kosaku
IAEA-TECDOC-784, 0, p.86 - 91, 1995/01
no abstracts in English
Minato, Kazuo; ; Fukuda, Kosaku; *; *; *; *
Nuclear Technology, 106, p.342 - 349, 1994/06
Times Cited Count：15 Percentile：77(Nuclear Science & Technology)no abstracts in English
Ogawa, Toru
Encyclopedia of Advanced Materials, 0, p.1793 - 1798, 1994/00
no abstracts in English
CMinato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; Sekino, Hajime; ; ;
Journal of Nuclear Materials, 202, p.47 - 53, 1993/00
Times Cited Count：60 Percentile：96.91(Materials Science, Multidisciplinary)no abstracts in English
Ogawa, Toru; Fukuda, Kosaku; Kashimura, Satoru; Tobita, Tsutomu; Kobayashi, Fumiaki; ; ; ; Kikuchi, Teruo
Journal of the American Ceramic Society, 75(11), p.2985 - 2990, 1992/11
Times Cited Count：41 Percentile：84.71(Materials Science, Ceramics)no abstracts in English
