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Reactions to Achieve Mass-spectrometric Discrimination in Simultaneous Plutonium-isotope Speciation with Inductively Coupled Plasma-Tandem Mass SpectrometryMatsueda, Makoto; Kawakami, Tomohiko*; Koarai, Kazuma; Terashima, Motoki; Fujiwara, Kenso; Iijima, Kazuki; Furukawa, Makoto*; Takagai, Yoshitaka*
Chemistry Letters, 51(7), p.678 - 682, 2022/07
Times Cited Count：5 Percentile：61.39(Chemistry, Multidisciplinary)New methodology for a simultaneous isotope speciation of various Pu isotopes without complicated isobaric interferences is developed by using inductively coupled plasma-mass spectrometry (ICP-MS). In analyzing ICP tandem MS (ICP-MS/MS), CO gas reactions in a dynamic reaction cell (DRC) almost eliminated the background noise intensity produced by isobaric interference from isotopes originating from actinides such as Am, Cm, and U at the locations (m/z) of significant Pu isotopes (
Pu, 
Pu, 
Pu, 
Pu, 
Pu).
Ozawa, Masaki; Suzuki, Tatsuya*; Koyama, Shinichi; Yamagishi, Isao; Fujita, Reiko*; Okada, Ken*; Tatenuma, Katsuyoshi*; Mimura, Hitoshi*; Fujii, Yasuhiko*
Proceedings of International Conference on Advanced Nuclear Fuel Cycle; Sustainable Options & Industrial Perspectives (Global 2009) (CD-ROM), p.1117 - 1126, 2009/09
Koyama, Shinichi; Ozawa, Masaki; Okada, Ken*; Kurosawa, Kiyoko*; Suzuki, Tatsuya*; Fujii, Yasuhiko*
Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1530 - 1536, 2007/09
Simplified separation process was proposed based on ion-exchange technique. HCl, HNO
and MeOH were used as an eluent. To develop an engineering scale concept, it is indispensable to establish the condition for safety operation. Corrosion test of structural materials in the HCl was performed by using some metals. In this experiment, it was proved that the Ta, Zr, Nb and hastelloy have good endurance to HCl solution. Research of thermal hazard of pyridine-type ion-exchange resin, MeOH and HNO media system was studied in the view point of fire and explosion safety. There is no hazardous reaction between IER/MeOH, HNO media system. In the case of more than 150
C, we should pay attention to the exothermic reaction at dried condition NO-IER or IER/HNO media system.
W/Re generatorsMatsuoka, Hiromitsu; Hashimoto, Kazuyuki; Hishinuma, Yukio*; Ishikawa, Koji*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*; Uchida, Shoji*
Journal of Nuclear and Radiochemical Sciences, 6(3), p.189 - 191, 2005/12
Applicability of Mo adsorbent PZC(Poly Zirconium Compound) for W/Re generator was investigated. Long term stability of adsorption of W to the PZC column, elution of Re from PZC column, desorption of 
from PZC column, and labeling of Hydroxyethylidene Diphosphonic Acid(HEDP) and Mercaptoacetyltriglycine(MAG3) with Re eluted from PZC column were tested. The PZC generator gave reproducible Re elution yields with low W parent breakthrough for a long period of time(about 5 months), that is the W/Re generator using PZC has a potential for practical use.
Terunuma, Hitoshi*; Arai, Osamu*
JNC TJ8400 2004-037, 73 Pages, 2004/02
In order to convert a salt waste from dry reprocessing to oxide for vitrification, a basic examination about the conversion reaction of chloride was performed. The salt waste simulator (chloride salt) was reacted with boron oxide and water vapor at 1023K-1123K, and converted to oxide with occurring of hydrogen chloride as by-product. the hydrogen chloride generated in this reaction was stabilized by hydrogen chloride stabilizer
Terunuma, Hitoshi*; Arai, Osamu*
JNC TJ8400 2001-056, 101 Pages, 2002/02
JNC-TJ8400-2001-056.pdf:8.13MB
Oxidation exchange treatment, chlorine is separated from salt wastes generated from dry reprocessing as a from of hydrogen chlolide by a reaction between salt waste and vapor at high temperature, was investigated for the purpose of adaptation of salt waste to the glassification. According to the last experiments, it has been clarified that the addition of boron oxide was effective to the oxidation exchange treatment of chloride. On the other hand, a phenomenon which chlolide is evaporated by high temperature and effused from the treatment was occurred. Therefore, this phenomenon has been a problem for the practical adaptation. In this study, experiments attach importance to the oxidation exchange of cesium chlolide, the fission products, were performed for the purposes of effective oxidation exchange treatment of chlolide and evaporation reduction of chloride. As a result of this experiment, the evaporation reduction of chlolide was confirmed by reconstructions of equipment such as a vessel for samples and a buffle plate. It has been clarified that nearly 100% of chloride could be separated from the salt waste by oxidation exchange treatment by addition of boron oxide, the oxidation stimulator, to a specimen of cesium chlolide and a mixed specimen of sodium chloride and cesium chloride. Furthermore, some amount of cesium and sodium were remained in the vessel for the treatment and the evaporation of chloride was depressed. Hydrosodalite was applied in order to adsorb and remove hydrogen chloride from the treated specimen, however, the effects of its was unknown and there was a problem that chloride is regenerated by the thermal separation.
Terunuma, Hitoshi*; Arai, Osamu*
JNC TJ8400 2001-004, 96 Pages, 2001/03
JNC-TJ8400-2001-004.pdf:8.13MB
For a purpose of glassification processing of the salt waste generated from the fused salt electrolysis method, one of the nuclear fuel reprocessing methods, a processing method to convert chloride to oxide which has an ability of high solubility to the glass was examined. Chloride, the main ingredient of the salt waste, was fused and reacted with water steam. Then the chlorine was separated as a form of hydrogen chloride. The examination was proceeded by an equipment consists of the following compositions. Water steam is generated from the moisture gas generator by the vapor pressure method. The steam is passed through the processing container where the imitation salt is fused and oxidized. Hydrogen chloride generated from the oxidation conversion of chloride is recovered in wet process by the gas scrubber. This examination was implemented under different conditions of imitation salt, processing temperature, water addition amount and presence of boron oxide addition for the stimulation of the oxidation. Volatilized salt steam switched over from the fused salt to the exhaust system, and it caused the plumbing blockade. This phenomenon exerted a big influence on the examination running. By adding boron oxide, percentage of the oxidation conversion increased from a few % to 50%. The oxide generated from processed salt by conversion could be confirmed. It showed that the addition of boron oxide is effective for oxidation conversion of chloride. However, boron oxide was added as the same amount as a commensurate mole of chloride in the imitation salt, and it causes to decline the processing quantity and to increase the amount of the waste evolution. An investigation of the optimal quantity of boron oxide addition will be a next problem to be solved in the future.
W/Re generatorHashimoto, Kazuyuki; Hishinuma, Yukio*; Ishikawa, Koji*; Terunuma, Hitoshi*; Tatenuma, Katsuyoshi*; Uchida, Shoji*; Matsuoka, Hiromitsu
no journal, ,
Applicability of Mo adsorbent PZC(Poly Zirconium Compound) for W/Re generator was investigated. Up to the present, long term stability of adsorption of W to the PZC column, elution of Re from PZC column, desorption of W from PZC column, and labeling of Hydroxyethylidene Diphosphonic Acid (HEDP) and Mercaptoacetyltriglycine (MAG3) with Re eluted from PZC column were tested and the results were compared with that of Re eluted from alumina column.
Ozawa, Masaki; Koyama, Shinichi; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Fujii, Yasuhiko*
no journal, ,
no abstracts in English
Koyama, Shinichi; Ozawa, Masaki; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*
no journal, ,
Corrosion experiments (Immersion, exposure and electro chemistry) in pure HCl and HCl type SHLLW solution at RT and 90C were performed using selected candidate metals, Ta, Zr, Nb and Hastelloy-B. We found the measured corrosion rates were less than 0.05 mm/y for Ta in all experiment, and therefore, Ta showed an all-round anti-corrosion property. Hastelloy-B, Nb and Zr were not acceptable at 90C because of its relatively high corrosion rate (
0.1 mm/y).
Tc generated from natural-Mo(n,
)
Mo, 4; Analysis in the verification test of the producing process of Tc milked from a highly radioactive MoSonoda, Takashi; Umeda, Miki; Tagami, Susumu; Kurobane, Shiro; Miyoshi, Yoshinori; Tanaka, Atsushi*; Ishikawa, Koji*; Tsuguchi, Akira*; Tatenuma, Katsuyoshi*
no journal, ,
no abstracts in English
Koyama, Shinichi; Ozawa, Masaki*; Fujii, Yasuhiko; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*
no journal, ,
In order to develop a separation process using tetriary pyridine-type resin, Ti-0.5Ps, Ta-lining Ti-0.15Pd and Ta-lining hastelloy-B were selected as candidate materials toward HCl solution used as solvent in this system. Immersion test in 12M pure HCl solution at RT was carried out. And immersion test, exposure test and electrochemical measurement in 7M HLLW-simulated HCl solution at RT and 90 deg. C were performed. As a result, all the materials show anti-corrosive property at the corrosion rate less than 1mm/y, except for Ti-0.5Pd in 12M pure HCl condition.
-ray irradiation to hydrochloric acid corrosion of Ta and Hastelloy-BKoyama, Shinichi; Fujii, Yasuhiko; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*
no journal, ,
Corrosion experiment for Ta and Hastelloy-B was performed by -ray irradiation under co-existence system of tertiary pyridine type resin and HCl media. As a result, Ta showed perfect anti-corrosion property under all experimental conditions. On the other hand, it was clear that the corrosion rate of Hastelloy-B was proportion to -ray intensity. It is expected that oxidative species, such as hydrogen peroxide and ozone, were produced by irradiation, and were affected to corrosion.
Koyama, Shinichi; Matsumura, Tatsuro; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*
no journal, ,
no abstracts in English
Koyama, Shinichi; Matsumura, Tatsuro; Kurosawa, Kiyoko*; Hanamoto, Yukio*; Tatenuma, Katsuyoshi*; Suzuki, Tatsuya*; Ozawa, Masaki*
no journal, ,
no abstracts in English
Abe, Yuta; Otaka, Masahiko; Okazaki, Kodai*; Kawakami, Tomohiko*; Oishi, Yuji*
no journal, ,
no abstracts in English
Okazaki, Kodai*; Kawakami, Tomohiko*; Abe, Yuta; Otaka, Masahiko; Oishi, Yuji*
no journal, ,
no abstracts in English
Segawa, Tomoomi; Kawaguchi, Koichi; Ishii, Katsunori; Nishina, Masahiro; Makino, Takayoshi; Natori, Yuri*; Ikemoto, Norihiro*; Yonehara, Kazuo*; Tatenuma, Katsuyoshi*
no journal, ,
Japan Atomic Energy Agency has researched and developed a simplified MOX pellet fabrication process. the flowability of MOX powder is improved by a tumbling granulation method using water as a binder. However, in this granulation method, improvement of the production capacity under criticality control for wet nuclear material is an issue. In recent years, an additive-free dry granulation technology has proposed as a novel granulation method for producing tritium breeding LiO spheres for nuclear fusion reactor. In this study, to confirm the applicability of this method to the MOX fuel fabrication process, CeO powder was used as a simulated material of MOX powder as a basic test for mechanization, and the influence of mechanical external force on granulation was confirmed and evaluated. As a result of the test, good granulation property was obtained by applying a mechanical external force of vertical vibration, and it was possible to obtain the prospect of mechanization of the dry granulation process.
