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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).

Journal Articles

Electro-deposition of tantalum on tungsten and nickel in LiF-NaF-CaF$$_{2}$$ melt containing K$$_{2}$$TaF$$_{7}$$; Electrochemical study

Mehmood, M.*; Kawaguchi, Nobuaki*; Maekawa, Hideki*; Sato, Yuzuru*; Yamamura, Tsutomu*; Kawai, Masayoshi*; Kikuchi, Kenji

Materials Transactions, 44(2), p.259 - 267, 2003/02

 Times Cited Count:9 Percentile:52.01(Materials Science, Multidisciplinary)

Electrochemical study has been carried out on the electro-deposition of tantalum in LiF-NaF-CaF$$_{2}$$ melt containing K$$_{2}$$TaF$$_{7}$$ at 700$$^{circ}$$C. This has been done for determining the mechanistic features for preparing electrolytic coating of tantalum on nickel and tungsten substrates. Electro-deposition of metallic tantalum occurs primarily by electro-reduction of Ta(V). Pure metallic tantalum without any entrapped salt is successfully deposited on tungsten by galvanostatic polarization at reasonably low current densities. An additional feature on nickel is the formation of an intermetallic compound at potential 0.25V nobler than that of pure tantalum as a result of underpotential deposition of tantalum. This intermetallic compound covers the surface within a short time followed by deposition of pure tantalum, although intermetallic compound keeps growing at the interface of pure tantalum deposit and the substrate as a result of diffusion.

JAEA Reports

Acceleration irradiation test of first-loading fuel of High Temperature Engineering Test Reactor (HTTR) up to high burnup (Joint research)

Sawa, Kazuhiro; Sumita, Junya; Ueta, Shohei; Takahashi, Masashi; Tobita, Tsutomu*; Hayashi, Kimio; Saito, Takashi; Suzuki, Shuichi*; Yoshimuta, Shigeharu*; Kato, Shigeru*

JAERI-Research 2002-012, 39 Pages, 2002/06

JAERI-Research-2002-012.pdf:3.12MB

no abstracts in English

Journal Articles

Coated fuel particle; Small particles for nuclear fuel

Minato, Kazuo

Zusetsu Zoryu; Tsubu No Sekai Arekore, p.131 - 133, 2001/10

no abstracts in English

JAEA Reports

Development of advanced fabrication technology for high-temperature gas-cooled reactor fuel; Reduction of coating failure fraction

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; Yoshimuta, Shigeharu*; *; *; *; *

JAERI-Research 98-070, 25 Pages, 1998/11

JAERI-Research-98-070.pdf:2.18MB

no abstracts in English

Journal Articles

Development of ceramic-coated lithium particles for tritium production tests in high temperature engineering test reactor

Yamashita, Kiyonobu; Sawa, Kazuhiro; Ando, Hiroei; *; *

Nihon Genshiryoku Gakkai-Shi, 40(1), p.65 - 69, 1998/00

 Times Cited Count:6 Percentile:49.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Improvements in quality of as-manufactured fuels for high-temperature gas-cooled reactors

Minato, Kazuo; ; Tobita, Tsutomu*; Fukuda, Kosaku; *; *; *; *

Journal of Nuclear Science and Technology, 34(3), p.325 - 333, 1997/03

 Times Cited Count:16 Percentile:75.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Advanced coatings for HTGR fuel particles against corrosion of SiC layer

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

Journal Articles

Failure mechanisms of fuel particle coating for high-temperature gas-cooled reactors during the coating processes

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

JAEA Reports

Air oxidation behavior of fuel for the High Temperature Engineering Test Reactor(HTTR)

; Hayashi, Kimio; Fukuda, Kosaku

JAERI-M 92-114, 20 Pages, 1992/08

JAERI-M-92-114.pdf:1.06MB

no abstracts in English

Journal Articles

Thermal response of ARIES-I divertor plate to plasma disruption

M.Z.Hasan*; Kunugi, Tomoaki; Seki, Masahiro; Yokokawa, Mitsuo; Ise, Hideo*; ;

Fusion Technology, 19, p.908 - 912, 1991/05

no abstracts in English

JAEA Reports

Waterproof effect of plastic coating on radioactive waste solids

*; *; *; *; Matsuzuru, Hideo

JAERI-M 89-200, 26 Pages, 1989/12

JAERI-M-89-200.pdf:0.98MB

no abstracts in English

JAEA Reports

Failure Mechnisms of Coaded Fuel particles During Fabrication

Minato, Kazuo; ; ;

JAERI-M 86-083, 27 Pages, 1986/06

JAERI-M-86-083.pdf:2.45MB

no abstracts in English

JAEA Reports

Thermal Cycle Testing of Tic-coated Molybdenum by Infrared Heating

JAERI-M 85-204, 7 Pages, 1985/12

JAERI-M-85-204.pdf:0.53MB

no abstracts in English

JAEA Reports

Journal Articles

Development of TiC-coated wall materials for JT-60

; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *

Journal of Nuclear Materials, 133-134, p.754 - 759, 1985/00

 Times Cited Count:16 Percentile:85.27(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Development of TiC coated wall materials for JT-60(I)-Program and progress in the technological development

; Murakami, Yoshio; ; Hiroki, S.; ; *; *; *; *

Shinku, 27(5), p.394 - 397, 1984/00

no abstracts in English

JAEA Reports

Experimental Studies of Scattered Particle Phenomena During In-Situ Coating Process

; ; ; ;

JAERI-M 83-087, 16 Pages, 1983/06

JAERI-M-83-087.pdf:0.6MB

no abstracts in English

29 (Records 1-20 displayed on this page)