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Journal Articles

Retention of uranium in cement systems; Effects of cement degradation and complexing ligands

Ochs, M.*; Vriens, B.*; Tachi, Yukio

Progress in Nuclear Science and Technology (Internet), 5, p.208 - 212, 2018/11

The clean-up activities related to the accident at the Fukushima Nuclear Power Plant give rise to several types of wastes containing cementitious materials, such as concrete. Further, the use of cement-based barriers may be considered, due to their favorable and stable chemical properties, including their ability to sorb or incorporate radionuclides. Wastes from Fukushima are expected to contain substances that can have perturbing effects on retention, especially organic complexing substances, boron, and chloride salts. The present study focuses on a methodology for quantifying the retention behaviour of UVI) and U(IV) in cement materials of different degradation and in the presence of organics, boron, and salts on the basis of available literature information. A stepwise approach is proposed and illustrated for Kd setting for U(VI) and U(IV).

Journal Articles

Research and development on nuclear transmutation, B; Transmutation fuel and reprocessing

Minato, Kazuo; Arai, Yasuo

Genshikaku Kenkyu, 47(6), p.31 - 38, 2003/06

no abstracts in English

Journal Articles

Recovery of U by electrolysis of UN in LiCl-KCl eutectic melts

Shirai, Osamu; Uozumi, Koichi*; Iwai, Takashi; Arai, Yasuo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.745 - 748, 2002/11

no abstracts in English

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.

JAEA Reports

Proceedings of the Workshop on Molten Salts Technology and Computer Simulation

Hayashi, Hirokazu; Minato, Kazuo

JAERI-Conf 2001-016, 181 Pages, 2001/12

JAERI-Conf-2001-016.pdf:11.72MB

Applications of molten salts technology to separations and syntheses of materials have been studied eagerly, which would develop new fields of materials science. Research Group for Actinides Science, Department of Materials Science, Japan Atomic Energy Research Institute (JAERI), together with Reprocessing and Recycle Technology Division, Atomic Energy Society of Japan, organized the Workshop on Molten Salts Technology and Computer Simulation at Tokai Research Establishment, JAERI on September 18, 2001. In the workshop eleven lectures were made and lively discussions were there on the bases and applications of the molten salts technology that covered the structure and basic properties of molten salts, the pyrochemical reprocessing technology and the relevant computer simulation.

Journal Articles

Dissolution and formation of nuclear materials in molten media

Ogawa, Toru; Minato, Kazuo

Pure and Applied Chemistry, 73(5), p.799 - 806, 2001/05

 Times Cited Count:15 Percentile:54.07(Chemistry, Multidisciplinary)

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

Present status of TRU fuels behavior analysis and their data bases

Ogawa, Toru

Shometsu Shori Kenkyu No Genjo; Atarashii Genshiryoku Gijutsu No Kanosei O Motomete, 0, p.117 - 124, 1994/08

no abstracts in English

Journal Articles

Thermal diffusivity measurement of molten alkali carbonate salts by use of a simple ceramic cell

; *; *; Katsuta, Hiroji

Thermal Conductivity,Vol.19, p.279 - 287, 1988/00

no abstracts in English

Journal Articles

Oxidation of zircaloy cladding in air

;

Journal of Nuclear Materials, 140, p.32 - 43, 1986/00

 Times Cited Count:13 Percentile:79.17(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Single-fluid-Type Accelerator Molten-Salt Breeder(AMSB)

Furukawa, Kazuo; *

JAERI-M 83-050, 43 Pages, 1983/03

JAERI-M-83-050.pdf:1.05MB

no abstracts in English

Journal Articles

Structural analysis of molten NaNO$$_{2}$$

; *; *; *; Furukawa, Kazuo; *

1st Int. Symp. on Molten Salt Chemistry, J-204, p.345 - 348, 1983/00

no abstracts in English

Journal Articles

Structural analyses of molten R$$_{2}$$SO$$_{4}$$,R=Li,Na,K,Cs and Ag

*; *; *; ; Furukawa, Kazuo

First Inter.Symp.on Molten Salt Chem.Technol.,J-207, p.354 - 357, 1983/00

no abstracts in English

Journal Articles

Comments on transport phenomena of ionic liquids

; Furukawa, Kazuo

First Inter.Symp.on Molten Salt Chem.Technol.,J-315, p.449 - 452, 1983/00

no abstracts in English

Journal Articles

X-ray diffraction analysis of molten potassium bromide

; Furukawa, Kazuo; *; *; *

J.Chem.Soc.,Faraday Trans.,1, 79, p.463 - 471, 1983/00

no abstracts in English

Journal Articles

Structural analysis of molten LiBr

; Furukawa, Kazuo; *; *

J.Chem.Soc.,Faraday Trans.,I, 78(5), p.1555 - 1560, 1982/00

no abstracts in English

Journal Articles

Density estimation of ionic melts

Furukawa, Kazuo; ; *

Nihon Kagakkai-Shi, (6), p.942 - 946, 1982/00

no abstracts in English

Journal Articles

Structures of molten alkali halides

Oono, Hideo; Furukawa, Kazuo

Nihon Kagakkai-Shi, (6), p.934 - 941, 1982/00

no abstracts in English

Journal Articles

Self-diffusion of alkaline and fluorine ions in molten alkali fuoride-beryllium fluoride mixture

*; ; Katsuta, Hiroji; Furukawa, Kazuo

Nihon Kagakkai-Shi, 6, p.956 - 960, 1982/00

no abstracts in English

Journal Articles

Self-diffusion of lithium,sodium,potassium and fluorine in a molten LiF+NaF+KF eutectic mixture

*; *; ; *; Furukawa, Kazuo

J.Chem.Soc.,Faraday Trans.,I, 77, p.169 - 175, 1981/00

no abstracts in English

45 (Records 1-20 displayed on this page)