Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 67

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

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

Development of silicon carbide coating on Al$$_{2}$$O$$_{3}$$ ceramics from precursor polymers by radiation curing

Wach, R.; Sugimoto, Masaki; Yoshikawa, Masahito

Key Engineering Materials, 317-318, p.573 - 576, 2006/08

no abstracts in English

Journal Articles

Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr$$_{2}$$O$$_{3}$$-SiO$$_{2}$$ including CrPO$$_{4}$$, Out-of-pile tests

Kulsartov, T. V.*; Hayashi, Kimio; Nakamichi, Masaru*; Afanasyev, S. E.*; Shestakov, V. P.*; Chikhray, Y. V.*; Kenzhin, E. A.*; Kolbaenkov, A. N.*

Fusion Engineering and Design, 81(1-7), p.701 - 705, 2006/02

 Times Cited Count:29 Percentile:10.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of reliable diamond window for EC launcher on fusion reactors

Takahashi, Koji; Illy, S.*; Heidinger, R.*; Kasugai, Atsushi; Minami, Ryutaro; Sakamoto, Keishi; Thumm, M.*; Imai, Tsuyoshi

Fusion Engineering and Design, 74(1-4), p.305 - 310, 2005/11

 Times Cited Count:13 Percentile:30.82(Nuclear Science & Technology)

A new diamond window with the copper-coated edge for an EC launcher is developed. The diamond window is designed to cool its disk edge. Since Cu is coated at the entire edge, ingress of cooling water into a transmission line in case of failure on the edge is negligible. In addition, corrosion of Al blaze between the edge and the Inconel cuffs can be avoided. A 170GHz, RF transmission experiment equivalent to a MW-level transmission was carried out to investigate the capability of the edge cooling. The transmission power and pulse are 55kW and 3sec, respectively. Temperature increase was 45$$^{circ}$$C and alomost became constant. Thermal calculation with tan$$delta$$ of 4.4$$times$$10$$^{-4}$$ and thermal conductivity of 1.9kW/m/K agrees with the experiment. Since tan$$delta$$ of the diamond is much higher than the actual one (tan$$delta$$=2$$times$$10$$^{-5}$$), the temperature increase corresponds to that of 1MW transmission. It concludes that the Cu coating dose not degrade the edge cooling capability and improves the reliability of the diamond window.

Journal Articles

Development of SiC coatings on Al$$_{2}$$O$$_{3}$$ ceramics from precursor polymers by radiation curing

Wach, R.; Sugimoto, Masaki; Lam, N. D.; Yoshikawa, Masahito

Proceedings of 8th SPSJ International Polymer Conference (IPC 2005) (CD-ROM), 60 Pages, 2005/07

no abstracts in English

JAEA Reports

An Irradiation experiment for qualification of insulating coating

Nakamichi, Masaru*; Kawamura, Hiroshi

JAERI-Research 2005-015, 35 Pages, 2005/06

JAERI-Research-2005-015.pdf:6.48MB

no abstracts in English

Journal Articles

Development of cold isostatic pressing graphite module for a heat-resistant lower hybrid current drive antenna

Maebara, Sunao; Goniche, M.*; Kazarian, F.*; Seki, Masami; Ikeda, Yoshitaka; Imai, Tsuyoshi*; Beaumont, B.*

Review of Scientific Instruments, 76(5), p.053501_1 - 053501_7, 2005/05

 Times Cited Count:1 Percentile:89.34(Instruments & Instrumentation)

Development of a plasma facing module using Cold Isostatic Pressing Graphite (CIPG) had been done for a heat-resistant LHCD antenna. A thin stainless film (10$$mu$$m), molybdenum film (10$$mu$$m) and copper film (50$$mu$$m) are laid to overlap each other on the CIPG materials, the CIPG surfaces were successfully coated with copper layer by diffusion bonding method. This module has four waveguides and a water cooling channel, the length is 206 mm. High power long pulse operation was successfully achieved up to 250 kW (125 MW/m$$^{2}$$)/700s. The module has been successfully tested at a RF power density which is equivalent, in terms of RF electric field (5kV/cm), to the one proposed for the LHCD antenna of ITER-FEAT. The outgassing rate of the copper-coated CIPG is estimated to be 3.2-5.1$$times$$10$$^{-6}$$ Pa.m$$^{3}$$/s.m$$^{2}$$ at 100$$^{circ}$$C, it is assessed that a pumping system is not required to evacuate the pressure in the LHCD antenna.

Journal Articles

Solid spallation target materials development

Kawai, Masayoshi*; Furusaka, Michihiro; Li, J.-F.*; Kawasaki, Akira*; Yamamura, Tsutomu*; Mehmood, M.*; Kurishita, Hiroaki*; Kikuchi, Kenji; Takenaka, Nobuyuki*; Kiyanagi, Yoshiaki*; et al.

Proceedings of ICANS-XVI, Volume 3, p.1087 - 1096, 2003/07

In order to establish the technique fabricating a thin target slab with a real size, thin tantalum-clad tungsten slab with a hole for a thermocouple was fabricated with the high-precision machinery techniques and the HIP'ing method. The ultrasonic diagnostic showed that tantalum and tungsten bond was perfect. The HIP optimum condition was certified by means of the small punch test as already reported. The electrolytic coating technique in a molten salt was developed to make a thinner tantalum cladding on a tungsten target with a complicated shape, in order to reduce radioactivity from tantalum in an irradiated target.

Journal Articles

R&D of a MW-class solid-target for spallation neutron source

Kawai, Masayoshi*; Furusaka, Michihiro*; Kikuchi, Kenji; Kurishita, Hiroaki*; Watanabe, Ryuzo*; Li, J.*; Sugimoto, Katsuhisa*; Yamamura, Tsutomu*; Hiraoka, Yutaka*; Abe, Katsunori*; et al.

Journal of Nuclear Materials, 318, p.35 - 55, 2003/05

R&D works for MW class solid target composed of tungsten to produce pulsed intense neutron source has been made in order to construct a future scattering facility. Three methods were investigated to prevent corrosion of tungsten from water; those are hipping, brazing and electric coating in molten salt bath. Hipping condition was optimized to be 1500 degree C in the previous work: here small punch test shows highest load for crack initiation of hipped materials at the boundary of W/Ta. The basic techniques for the other two methods were developed. Erosion test showed that uncovered W is susceptible of flowing water velocity. At high velocity w is easy to be eroded. For solid target design slab type and rod type targets were studied. As long as the optimized neutron performance is concerned, 1MW solid target is better than mercury target.

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:5 Percentile:58.74(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.

Journal Articles

Disruption tests on repaired tungsten by CVD coating

Taniguchi, Masaki; Sato, Kazuyoshi; Ezato, Koichiro; Yokoyama, Kenji; Akiba, Masato

Journal of Nuclear Materials, 307-311(Part1), p.719 - 722, 2002/12

 Times Cited Count:18 Percentile:24.43

no abstracts in English

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

Modeling of fuel performance and fission product release behaviour during HTTR normal operation; A Comparative study on the FZJ and JAERI Modeling approach

Verfondern, K.*; Sumita, Junya; Ueta, Shohei; Sawa, Kazuhiro

JAERI-Research 2000-067, 127 Pages, 2001/03

JAERI-Research-2000-067.pdf:6.64MB

no abstracts in English

Journal Articles

Evaluation tritium transportation to the product hydrogen in the HTGR hydrogen production system

Nishihara, Tetsuo; Hada, Kazuhiko

Nippon Genshiryoku Gakkai-Shi, 41(5), p.571 - 578, 1999/05

 Times Cited Count:5 Percentile:57.45(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Compact and high repetitive photodiode array detector for the JT-60U Thomson scattering diagnostic

Yoshida, Hidetoshi; Naito, Osamu; *; Kitamura, Shigeru; Hatae, Takaki; Nagashima, Akira

Review of Scientific Instruments, 70(1), p.747 - 750, 1999/01

 Times Cited Count:4 Percentile:60.41(Instruments & Instrumentation)

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

JAEA Reports

Durability of alumina electrical insulation films by plasma spraying coating method under repeated impact loads

Kanari, Moriyasu*; Abe, Tetsuya; Enoeda, Mikio; *; *; Shimizu, Katsusuke*; *; Takatsu, Hideyuki

JAERI-Research 98-029, 23 Pages, 1998/06

JAERI-Research-98-029.pdf:2.51MB

no abstracts in English

67 (Records 1-20 displayed on this page)