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Sato, Isamu; Maeda, Koji; Suto, Mitsuo; Osaka, Masahiko; Usuki, Toshiyuki; Koyama, Shinichi
Journal of Nuclear Science and Technology, 52(4), p.580 - 587, 2015/04
Times Cited Count：6 Percentile：45.29(Nuclear Science & Technology)Penetration behavior of radionuclides such as 
Cs into dried concrete material, dried mortar material and epoxy paint for a few dozen days was observed using a solution containing fission products extracted from irradiated fuels to obtain fundamental information on the radionuclide penetration rate and depth. Hardly any radionuclides could penetrate into the epoxy paint. The radionuclide solution penetrated into concrete and mortar materials to a depth of a few millimeters for a few dozen days. The penetration behavior observed near the surface of concrete and mortar materials was similar to the diffusion of nuclides in media such as water-saturated concrete, bentonite and cement materials.
Usuki, Toshiyuki; Sato, Isamu; Suto, Mitsuo; Maeda, Koji; Osaka, Masahiko; Koyama, Shinichi; Tokoro, Daishiro*; Sekioka, Ken*; Ishigamori, Toshio*
JAEA-Testing 2014-001, 29 Pages, 2014/05
JAEA-Testing-2014-001.pdf:5.33MB
The penetration tests with solution containing radioactive nuclides were experimented to understand basic data for floor and wall materials of Fukushima Daiichi reactor buildings. The solution prepared from irradiated fuels was used as solution containing radioactive nuclides. The solution was applied to surface of epoxy paint, dried concrete and mortar used as specimens. Dose-rate profiles of direction of depth were given by radiation measurement and grinding of the specimens. The penetrations of radioactive nuclides for epoxy paint specimens were not clearly observed and the penetration depths would be within 0.4 mm. The penetrations of radioactive nuclides for dried concrete specimens proceeded. The penetration rates were substantially decreased when 16 days have elapsed from start. The dose rates of penetrated dried concrete specimens were reduced to background by grinding-2.0 mm. 
-ray spectrometry measurement showed that penetration behavior of near surface concrete are different among nuclides and the penetration behavior of radioactive nuclides into dried concrete and mortar materials through solution is similar to migration behavior of ions into those water-saturated materials.
Miwa, Shuhei; Osaka, Masahiko; Usuki, Toshiyuki; Sato, Isamu; Tanaka, Kosuke; Hirosawa, Takashi; Yoshimochi, Hiroshi; Onose, Shoji
Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 8 Pages, 2011/12
A new fast reactor (FR) cycle concept was previously proposed that incorporates MgO-based inert matrix fuels (IMFs) containing minor actinides harmonious with the existing FR cycle technologies. A basic study of MgO-based IMFs was made regarding their fabrication, characterization and reprocessing in terms of applicability to existing FR cycle technology. It was concluded from these basic investigations of MgO-based IMFs that the existing FR cycle technologies can be applied to those for MgO-based IMFs, and the basic technologies of MgO-based IMFs containing minor actinides harmonious with the existing FR cycle technologies were established.
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：18.18(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
solution was tested. Effects of impurities in recovered Mo on sintering behavior were experimentally investigated.
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.
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), steatite (MgSiO) and forsterite (Mg
SiO
), on the fabrication properties and characteristics of the silicon nitride ceramics based inert matrix fuels were experimentally investigated. CeO was selected as simulating element of AmO. 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.
SbTe
; Ring statistics analogy between the crystal and amorphous statesKohara, Shinji*; Kato, Kenichi*; Kimura, Shigeru*; Tanaka, Hitoshi*; Usuki, Takeshi*; Suzuya, Kentaro; Tanaka, Hiroshi*; Moritomo, Yutaka*; Matsunaga, Toshiyuki*; Yamada, Noboru*; et al.
Applied Physics Letters, 89(20), p.201910_1 - 201910_3, 2006/11
Times Cited Count：204 Percentile：97.89(Physics, Applied)The three-dimensional atomic configuration of amorphous GeSbTe were derived by reverse Monte Carlo simulation with synchrotron-radiation X-ray diffraction data. The authors found that amorphous GeSbTe can be regarded as "even-numbered ring structure", because the ring statistics is dominated by four- and six-fold rings analogous to the crystal phase. On the other hand, the formation of Ge-Ge homopolar bonds in amorphous GeTe constructs both odd- and even-numbered rings. They believe that the unusual ring statistics of amorphous GeSbTe is the key for the fast crystallization speed of the material.
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 (SiN) 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), steatite (MgSiO) and forsterite (MgSiO), as additives. The sintered densities of SiN-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.
Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*
no journal, ,
Thermal conductivies of MgO-based inert matrix fuels containing PuO using the asbestos waste-derived ceramics as a sintering additive were experimentally investigated. Thermal diffusivities of fuels were measured by laser flush method. The effects of the MgO-SiO compound additives addition on the thermal conductivity were discussed.
Usuki, Toshiyuki*; Yoshida, Katsumi*; Imai, Masamitsu*; Yano, Toyohiko*; Miwa, Shuhei; Osaka, Masahiko
no journal, ,
no abstracts in English
Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.
no journal, ,
no abstracts in English
Miwa, Shuhei; Osaka, Masahiko; Usuki, Toshiyuki*; Yano, Toyohiko*
no journal, ,
no abstracts in English
Miwa, Shuhei; Usuki, Toshiyuki; Sato, Isamu; Hirosawa, Takashi; Tanaka, Kosuke; Osaka, Masahiko; Seki, Takayuki*; Kashimura, Naoki*
no journal, ,
no abstracts in English
Isozaki, Ryosuke; Katsuyama, Kozo; Tanaka, Kosuke; Sato, Isamu; Usuki, Toshiyuki; Sekio, Yoshihiro; Hayashi, Takehiro; Tokoro, Daishiro*
no journal, ,
no abstracts in English
Usuki, Toshiyuki; Sato, Isamu; Kanayama, Fumihiko; Suto, Mitsuo; Maeda, Koji; Koyama, Shinichi; Kawatsuma, Shinji; Fukushima, Mineo; Tokoro, Daishiro*; Sekioka, Ken*; et al.
no journal, ,
no abstracts in English
