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Journal Articles

Study on plutonium burner high temperature gas-cooled reactor in Japan; Introduction scenario, reactor safety and fabrication tests of the 3S-TRISO fuel

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:0 Percentile:100(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$$_{2}$$) 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.

Journal Articles

Development of security and safety fuel for Pu-burner HTGR; Test and characterization for ZrC coating

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).

Journal Articles

Study on Pu-burner high temperature gas-cooled reactor in Japan; Test and characterization for ZrC coating

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$$_{2}$$) 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$$_{2}$$-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.

Journal Articles

Development of security and safety fuel for Pu-burner HTGR, 5; Test and characterization for ZrC coating

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).

JAEA Reports

Plan to development of ZrC-TRISO coated fuel particle and construction of ZrC coater

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

Journal Articles

Retention of fission product cesium in ZrC coated fuel particles for high-temperature gas-cooled reactors

Minato, Kazuo; Ogawa, Toru; Koya, Toshio; Sekino, Hajime; Tomita, Takeshi

Journal of Nuclear Materials, 279(2-3), p.181 - 188, 2000/06

 Times Cited Count:32 Percentile:11.15

no abstracts in English

Journal Articles

Irradiation experiment of ZrC-coated fuel particles for high-temperature gas-cooled reactors

Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro; Ishikawa, Akiyoshi; Tomita, Takeshi; Iida, Shozo; Sekino, Hajime

Nuclear Technology, 130(3), p.272 - 281, 2000/06

 Times Cited Count:60 Percentile:3.7(Nuclear Science & Technology)

no abstracts in English

Journal Articles

ZrC-coated particle fuel for high temperature gas-cooled reactors

Minato, Kazuo; Ogawa, Toru; Sawa, Kazuhiro; Sekino, Hajime; Koya, Toshio; Kitagawa, Isamu; Ishikawa, Akiyoshi; Tomita, Takeshi;

Proc. of the Int. Conf. on Future Nuclear Systems (GLOBAL'99)(CD-ROM), 8 Pages, 1999/00

no abstracts in English

Journal Articles

Deterioration of ZrC-coated fuel particle caused by failure of pyrolytic carbon layer

Minato, Kazuo; Fukuda, Kosaku; Sekino, Hajime; Ishikawa, Akiyoshi;

Journal of Nuclear Materials, 252, p.13 - 21, 1998/00

no abstracts in English

Journal Articles

Fission product release from ZrC-coated fuel particles during post-irradiation heating at 1800 and 2000$$^{circ}$$C

Minato, Kazuo; Ogawa, Toru; Fukuda, Kosaku; Sekino, Hajime; Kitagawa, Isamu; Mita, Naoaki

Journal of Nuclear Materials, 249(2-3), p.142 - 149, 1997/00

 Times Cited Count:54 Percentile:4.18

no abstracts in English

JAEA Reports

Review of experimental studies of zirconium carbide coated fuel particles for high temperature gas-cooled reactors

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

Journal Articles

Thermodynamic analysis of behavior of HTGR fuel and fission products under accidental air or water ingress conditions

Minato, Kazuo; Fukuda, Kosaku

IAEA-TECDOC-784, 0, p.86 - 91, 1995/01

no abstracts in English

Journal Articles

Performance of ZrC-coated particle fuel in irradiation and postirradiation heating tests

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:35 Percentile:16.72(Materials Science, Ceramics)

no abstracts in English

JAEA Reports

Integrity assessment of test fuel assemblies of the High Temperature Engineering Test Reactor

; Shiozawa, Shusaku; Fukuda, Kosaku; Tsuruta, Harumichi; Ikawa, Katsuichi; *; ; Tobita, Tsutomu; Shiratori, Tetsuo; Akabori, Mitsuo; et al.

JAERI-M 90-115, 77 Pages, 1990/07

JAERI-M-90-115.pdf:2.65MB

no abstracts in English

Journal Articles

Developing ZrC coatings for nuclear fue l particles

Ogawa, Toru; Fukuda, Kosaku

Surface Modification Technologies,III, p.309 - 320, 1990/00

no abstracts in English

Journal Articles

Coating microspheres with zirconium carbide-carbon composite by the methylene dichloride process

Ikawa, Katsuichi; Iwamoto, K.

Yogyo Kyokia-Shi, 81(938), p.403 - 406, 1973/10

no abstracts in English

Journal Articles

Coating microspheres with zirconium carbide

Ikawa, Katsuichi; Iwamoto, K.

Journal of Nuclear Materials, 45(1), p.67 - 68, 1972/01

 Times Cited Count:17

no abstracts in English

17 (Records 1-17 displayed on this page)
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