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Journal Articles

Reformation of hazardous wastes into useful supporting materials for fast reactor fuels

Osaka, Masahiko; Miwa, Shuhei; Tanaka, Kosuke; Akutsu, Yoko; Ikeda, Kaoru*; Mimura, Hitoshi*; Suzuki, Tatsuya*; Usuki, Toshiyuki; Yano, Toyohiko*

Annals of Nuclear Energy, 38(12), p.2661 - 2666, 2011/10

 Times Cited Count:2 Percentile:20.43(Nuclear Science & Technology)

Novel concepts for effective utilization of molybdenum (Mo) from nuclear waste and magnesium silicates from hazardous asbestos wastes are proposed. A fast reactor cycle scheme that incorporates each material is described in the present paper. Basic studies on some fundamental technologies for the present cycle are given. Basic separation aspects for Mo by using LIX63 micro capsules and tertiary pyridine resin were investigated. A simple chemical synthesis route for Mo precursor powder from Mo containing HNO$$_{3}$$ solution was tested. Effects of impurities in recovered Mo on sintering behavior were experimentally investigated.

Journal Articles

Fabrication and characterization of silicon nitride-based inert matrix fuels sintered with magnesium silicates

Usuki, Toshiyuki; Yoshida, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko

Progress in Nuclear Energy, 53(7), p.1078 - 1081, 2011/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The effects of sintering additives of magnesium silicates, i.e. enstatite (MgSiO$$_{3}$$), steatite (MgSiO$$_{3}$$) and forsterite (Mg$$_{2}$$SiO$$_{4}$$), on the fabrication properties and characteristics of the silicon nitride ceramics based inert matrix fuels were experimentally investigated. CeO$$_{2}$$ was selected as simulating element of AmO$$_{2}$$. Sintered pellets were characterized in term of their densities, thermal conductivities and solubility to nitric acid. The densifications of sintered bodies were enhanced by using additives of magnesium silicates at relative low sintering temperature. The relative density of silicon nitride ceramics based inert matrix fuels with forsterite were achieved above 90% at 1723 K. The thermal conductivities of silicon nitride ceramics based inert matrix fuels varied according to sintering temperature, and those sintered at 1923 K were above 34 W/m K. The grain boundary phases in Silicon nitride ceramics based inert matrix fuels found to be dissolved into HNO$$_{3}$$.

Journal Articles

Densification of magnesia-based inert matrix fuels using asbestos waste-derived materials as a sintering additive

Miwa, Shuhei; Osaka, Masahiko; Usuki, Toshiyuki; Yano, Toyohiko*

Progress in Nuclear Energy, 53(7), p.1045 - 1049, 2011/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

We proposed a new concept for densification of minor actinides-containing inert matrix fuels by using asbestos waste-derived materials for the effective utilization of resources and protection of public safety. In this concept, magnesium silicates, which are mainly generated by the decomposition of asbestos in low temperature heat-treatment, are used as a sintering additive for the achievement of high density of magnesia-based inert matrix fuels at relatively low sintering temperature. In this study, preliminary fabrication tests of magnesia-based inert matrix fuels with magnesium silicates were carried out by using cerium oxides as a representative of minor actinides oxides.

JAEA Reports

Development of Manufacturing Processes of Am-Bearing Target Materials Based on Si$$_{3}$$N$$_{4}$$ Inert Matrix

Yano, Toyohiko*; Osaka, Masahiko; Namekawa, Takashi

JNC TY9400 2004-002, 84 Pages, 2004/03

JNC-TY9400-2004-002.pdf:5.9MB

None

Journal Articles

Interstitial atom behavior in neutron irradiated beta-silicon nitride.

Akiyoshi, Masafumi; Akasaka, Naoaki; Tachi, Yoshiaki; Yano, Toyohiko*

Abstract p303,22-P-02, 303 Pages, 2003/00

Focusing on the cover layer materials (as the Radon Barrier Materials), which could have the effect to restrain the radon from scattering into the air and the effect of the radiation shielding, we produced the radon barrier materials with crude bentonite on an experimental basis, using the rotary type comprehensive unit for grinding and mixing, through which we carried out the evaluation of the characteristics thereof.

JAEA Reports

Research on the behavior of polonium produced in lead-bismuth eutectic irradiated with neutrons, JAERI's nuclear research promotion program, H10-026 (Contract research)

Sekimoto, Hiroshi*; Igashira, Masayuki*; Yano, Toyohiko*; Obara, Toru*; Osaki, Toshiro*

JAERI-Tech 2002-008, 58 Pages, 2002/03

JAERI-Tech-2002-008.pdf:3.6MB

no abstracts in English

JAEA Reports

An Investigation on high-temperature irradiation test program on new ceramic materials

Ishino, Shiori*; Terai, Takayuki*; Oku, Tatsuo*; Arai, Taketoshi; Hayashi, Kimio; Ito, Hisayoshi; Yano, Toyohiko*; Motohashi, Yoshinobu*; *; *; et al.

JAERI-Review 99-019, 238 Pages, 1999/08

JAERI-Review-99-019.pdf:14.88MB

no abstracts in English

Oral presentation

Characterization of silicon nitride ceramics sintered at lower temperatures with CeO$$_{2}$$, UO$$_{2}$$ or PuO$$_{2}$$ as a simulant for minor actinides

Yamane, Junichi*; Imai, Masamitsu*; Furuta, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko

no journal, , 

Silicon nitride is a promising candidate to hold those nuclei for transmutation. Silicon nitride ceramics with CeO$$_{2}$$, UO$$_{2}$$ or PuO$$_{2}$$ as a simulant for minor actinides were fabricated through a simple powder metallurgy process.

Oral presentation

Densification of nuclear fuel pellets using asbestos waste as a sintering additive

Miwa, Shuhei; Osaka, Masahiko; Usuki, Toshiyuki*; Yano, Toyohiko*

no journal, , 

no abstracts in English

Oral presentation

Fundamental study of inert matrix fuels adaptable to a fast reactor cycle system, 1; Concept

Osaka, Masahiko; Miwa, Shuhei; Kurosaki, Ken*; Yamanaka, Shinsuke*; Uno, Masayoshi*; Yamane, Yoshihiro*; Mimura, Hitoshi*; Yano, Toyohiko*

no journal, , 

Inert matrix fuel concept that is adaptable to the fast reactor cycle system was proposed. The concept has unique characteristics of a flexible management of minor actinides and effective utilization of beneficial materials in the nuclear cycle.

Oral presentation

Fundamental study of inert matrix fuels adaptable to a fast reactor cycle system, 2; Si$$_{3}$$N$$_{4}$$-based fuels

Yano, Toyohiko*; Yoshida, Katsumi*; Imai, Masamitsu*; Miwa, Shuhei; Osaka, Masahiko

no journal, , 

no abstracts in English

Oral presentation

Sintering and characterization of silicon nitride ceramics as inert matrix with magnesium silicates

Usuki, Toshiyuki*; Yoshida, Katsumi*; Imai, Masamitsu*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko

no journal, , 

no abstracts in English

Oral presentation

Sintering and characterization of silicon nitride ceramics as inert matrix with magnesium silicates

Usuki, Toshiyuki; Yoshida, Katsumi*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko

no journal, , 

Minor actinides (MA) have lasting radio-toxicity. One of the possible ways to reduce radio-toxicity is transmutation of MA using nuclear reactors. Inert matrix (IM) is applied to host material for MA in transmutation. Silicon nitride (Si$$_{3}$$N$$_{4}$$) ceramics considered to be a candidate material of IM since it has a high thermal conductivity and shows good resistance to neutron irradiation. In this study, We proposed fabrication of silicon nitride ceramics based IMFs with Ce as simulating element and with magnesium silicates, i.e. enstatite (MgSiO$$_{3}$$), steatite (MgSiO$$_{3}$$) and forsterite (Mg$$_{2}$$SiO$$_{4}$$), as additives. The sintered densities of Si$$_{3}$$N$$_{4}$$-based IMFs with forsterite was above 96 % theoretical 1723 K. Furthermore, The thermal conductivities of IMFs sintered at 1923 K were above 34 W/mK.

Oral presentation

Effective utilization of asbestos as useful supporting materials for fast reactor fuels

Osaka, Masahiko; Miwa, Shuhei; Yano, Toyohiko*

no journal, , 

Novel concept for effective utilization of magnesium silicates recovered from hazardous asbestos-derived wastes has been proposed. Basic studies on sintering behavior of the inert matrix-type fuel (IMF) including the asbestos waste-derived materials as sintering additives were carried out. Three types of IMFs were tested; MgO, Si$$_{3}$$N$$_{4}$$ and Mo-based IMFs. Effects of the additive on both the inert matrices and actinide oxides were experimentally investigated. Quantitative effects of the additives on the sintering densities of the IMFs were elucidated. Effects of additives on the sintering behavior were discussed in terms of high temperature chemistry. It was found that the asbestos-derived material, magnesium silicates, can control the sintered density of several types of nuclear fuel pellets. This concept potentially interconnects a hazardous social problem of asbestos to the nuclear fuel cycle issues.

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