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Journal Articles

Dissolution of uranium nitrides in LiCl-KCl eutectic melt

Hayashi, Hirokazu; Kobayashi, Fumiaki; Ogawa, Toru; Minato, Kazuo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.624 - 627, 2002/11

The behavior of the dissolution of uranium nitrides, which is a component of the MA-U mixed nitride fuel, has been investigated. A mixture of uranium nitride, LiCl-KCl and CdCl$$_2$$ was contained in a double walled quartz reaction vessel. During the heating, the carrier gas helium was introduced to a gas chromatography apparatus equipped with an automatic gas sampler. A fraction of the gas was sampled and analyzed by a mass analyzer. Most of nitrogen is recovered as N$$_2$$ gas from uranium nitrides dissolving in the LiCl-KCl eutectic melt reacted with CdCl$$_2$$ above 550 $$^o$$C, which is higher than that for lanthanide nitrides.

Journal Articles

The Standard molar enthalpy of formation of UNCl

Akabori, Mitsuo; Kobayashi, Fumiaki; Hayashi, Hirokazu; Ogawa, Toru; Huntelaar, M. E.*; Booij, A. S.*; Vlaanderen, P. van*

Journal of Chemical Thermodynamics, 34(9), p.1461 - 1466, 2002/09

 Times Cited Count:0 Percentile:0.02(Thermodynamics)

no abstracts in English

JAEA Reports

Journal Articles

Structure and dynamic properties of molten uranium trichloride

Okamoto, Yoshihiro; Kobayashi, Fumiaki; Ogawa, Toru

Journal of Alloys and Compounds, 271-273, p.355 - 358, 1998/00

 Times Cited Count:40 Percentile:86.02(Chemistry, Physical)

no abstracts in English

Journal Articles

Stability of UNCl in LiCl-KCl eutectic melt

Kobayashi, Fumiaki; Ogawa, Toru; Okamoto, Yoshihiro; Akabori, Mitsuo

Journal of Alloys and Compounds, 271-273, p.374 - 377, 1998/00

 Times Cited Count:8 Percentile:52.63(Chemistry, Physical)

no abstracts in English

Journal Articles

Actinide nitrides and nitride-halides in high-temperature systems

Ogawa, Toru; Kobayashi, Fumiaki; Sato, Tadashi; R.G.Haire*

Journal of Alloys and Compounds, 271-273, p.347 - 354, 1998/00

 Times Cited Count:16 Percentile:68.02(Chemistry, Physical)

no abstracts in English

Journal Articles

Thermochemical modeling of actinide alloys related to advanced fuel cycles

Ogawa, Toru; Akabori, Mitsuo; R.G.Haire*; Kobayashi, Fumiaki

Journal of Nuclear Materials, 247, p.215 - 221, 1997/00

 Times Cited Count:11 Percentile:65.46(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Dense fuel cycles for actinide burning and thermodynamic database

Ogawa, Toru; ; Kobayashi, Fumiaki; Ito, Akinori; Mukaiyama, Takehiko; Handa, Nuneo; R.G.Haire*

Global 1995,Int. Conf. on Evaluation of Emerging Nuclear Fuel Cycle Systems, 1, p.207 - 214, 1995/00

no abstracts in English

Journal Articles

Anodic dissolution of uranium mononitride in lithium chloride-potassium chloride eutectic melt

Kobayashi, Fumiaki; Ogawa, Toru; Akabori, Mitsuo;

Journal of the American Ceramic Society, 78(8), p.2279 - 2281, 1995/00

 Times Cited Count:21 Percentile:68.86(Materials Science, Ceramics)

no abstracts in English

JAEA Reports

Irradiation experiments of the 6th$$sim$$12th OGL-1 Fuel Assemblies

Hayashi, Kimio; Minato, Kazuo; Kobayashi, Fumiaki; ; Fukuda, Kosaku; Kikuchi, Teruo; ;

JAERI-Research 94-017, 250 Pages, 1994/10

JAERI-Research-94-017.pdf:17.08MB

no abstracts in English

JAEA Reports

Design of High Temperature Engineering Test Reactor (HTTR)

Saito, Shinzo; Tanaka, Toshiyuki; Sudo, Yukio; Baba, Osamu; Shindo, Masami; Shiozawa, Shusaku; Mogi, Haruyoshi; Okubo, Minoru; Ito, Noboru; Shindo, Ryuichi; et al.

JAERI 1332, 247 Pages, 1994/09

JAERI-1332.pdf:11.53MB

no abstracts in English

Journal Articles

Effect of neutron irradiation on length, thermal expansivity and thermal conductivity of boronated graphites

Matsuo, Hideto; Kobayashi, Fumiaki; Sawa, Kazuhiro

Tanso, 0(159), p.185 - 191, 1993/00

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:40 Percentile:84.42(Materials Science, Ceramics)

no abstracts in English

JAEA Reports

An Inspection standard of fuel for the High Temperature Engineering Test Reactor

Kobayashi, Fumiaki; Shiozawa, Shusaku; Hayashi, Kimio; Sawa, Kazuhiro; ; Fukuda, Kosaku; *; Sato, Tsutomu*

JAERI-M 92-079, 75 Pages, 1992/06

JAERI-M-92-079.pdf:1.73MB

no abstracts in English

JAEA Reports

An Examination on the determination precision of uranium content in the HTGR fuel compacts

Kobayashi, Fumiaki; Ito, Mitsuo; Suzuki, Shuichi*; Fukuda, Kosaku; *

JAERI-M 92-046, 18 Pages, 1992/04

JAERI-M-92-046.pdf:0.64MB

no abstracts in English

Journal Articles

Stability and structure of the $$delta$$ phase of the U-Zr alloys

Akabori, Mitsuo; Ito, Akinori; Ogawa, Toru; Kobayashi, Fumiaki;

Journal of Nuclear Materials, 188, p.249 - 254, 1992/00

 Times Cited Count:65 Percentile:97.39(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Release of short-lived noble gases from HTGR fuel with failed coated fuel particles and contaminated matrix

Ogawa, Toru; Kobayashi, Fumiaki; Tobita, Tsutomu; Fukuda, Kosaku; Saito, Takashi; Yokouchi, Iichiro;

Nucl. Eng. Des., 132, p.31 - 37, 1991/00

 Times Cited Count:10 Percentile:72.13(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of fuel failure detection system for a high temperature gas cooled reactor, IV

Katagiri, Masaki; Kishimoto, Maki; Terada, Hiromi; ; *; ; Ito, Hirokuni; ; Kobayashi, Fumiaki

IEEE Transactions on Nuclear Science, 37(3), p.1400 - 1404, 1990/06

 Times Cited Count:3 Percentile:45.11(Engineering, Electrical & Electronic)

no abstracts in English

JAEA Reports

On fabrication of UO$$_{2}$$ microspheres by internal gelation process

X.Cao*; Minato, Kazuo; Kobayashi, Fumiaki; Fukuda, Kosaku

JAERI-M 89-180, 14 Pages, 1989/11

JAERI-M-89-180.pdf:0.88MB

no abstracts in English

JAEA Reports

Design criteria, production and total integrity assessment of fuels of the High Temperature Engineering Test Reactor

Hayashi, Kimio; Shiozawa, Shusaku; Sawa, Kazuhiro; ; Maruyama, So; Kobayashi, Fumiaki; Fukuda, Kosaku

JAERI-M 89-161, 86 Pages, 1989/10

JAERI-M-89-161.pdf:2.25MB

no abstracts in English

46 (Records 1-20 displayed on this page)