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Journal Articles

Validation of ecological $$^{131}$$I transfer models using experimental data of the "Plavsk scenario"

Zvonova, I.*; Krajewski, P.*; Berkovskyy, V.*; Ammann, M.*; Duffa, C.*; Filistovic, V.*; Homma, Toshimitsu; Kany$'a$r, B.*; Nedveckaite, T.*; Simon, S.*; et al.

Proceedings of 7th International Conference on Nuclear and Radiochemistry (NRC-7) (CD-ROM), 5 Pages, 2008/08

Journal Articles

Chemical studies on rutherfordium (Rf) at JAERI

Nagame, Yuichiro; Tsukada, Kazuaki; Asai, Masato; Toyoshima, Atsushi; Akiyama, Kazuhiko; Ishii, Yasuo; Sato, Tetsuya; Hirata, Masaru; Nishinaka, Ichiro; Ichikawa, Shinichi; et al.

Radiochimica Acta, 93(9-10), p.519 - 526, 2005/00

 Times Cited Count:31 Percentile:87.03(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

A Systematic Study on Cesium Sorption on a Sedimentary Rock towards Reliable Safety Assessment Methodology for HLW Disposal

Xia, X.; Shibata, Masahiro; Kitamura, Akira; Kamei, Gento

P.779-781, p.779 - 781, 2004/08

A systematic sorption study on cesium, predicted to be a key radionuclide in the current safety assessment, was conducted on the sedimentary rock from the Horonobe URL, as the first step of linking sorption study in laboratory and modeling prediction of sorption at site.

Journal Articles

Startup of transactinide chemistry in JAERI

Haba, Hiromitsu; Tsukada, Kazuaki; Asai, Masato; Nishinaka, Ichiro; Sakama, Minoru*; Goto, Shinichi*; Hirata, Masaru; Ichikawa, Shinichi; Nagame, Yuichiro; Kaneko, Tetsuya*; et al.

Radiochimica Acta, 89(11-12), p.733 - 736, 2002/02

 Times Cited Count:15 Percentile:68.91(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Characteristics of two fission modes

Nagame, Yuichiro; Zhao, Y.*; Nishinaka, Ichiro; Goto, Shinichi*; Kaji, D.*; Tanikawa, Masashi*; Tsukada, Kazuaki; Asai, Masato; Haba, Hiromitsu; Sakama, Minoru*; et al.

Radiochimica Acta, 89(11-12), p.681 - 688, 2002/02

 Times Cited Count:3 Percentile:27.07(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Production of positron emitters of metallic elements to study plant uptake and distribution

Watanabe, Satoshi; Ishioka, Noriko; Osa, Akihiko; Koizumi, Mitsuo; Sekine, Toshiaki; Kiyomiya, Shoichiro*; Nakanishi, Hiromi*; Mori, Satoshi*

Radiochimica Acta, 89(11-12), p.853 - 858, 2002/02

 Times Cited Count:17 Percentile:74.75(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Phoswich detection system applying optical techniques for actinide monitoring

Usuda, Shigekazu; Yasuda, Kenichiro

Proceedings of 5th International Conference on Nuclear and Radiochemistry (NRC5), 2, p.595 - 598, 2000/00

no abstracts in English

Journal Articles

The Study of In Situ Radionuclide Retardation in the Geosphere: Examples from Nagra's Grimsel Test Site, Switzerland

; McKinl, I. G.*; Mori, A.*; Frieg, B.*; W.Kickmaie*

Proceedings of International Conference on Nuclear and Radiochemistry, 0 Pages, 2000/00

None

Oral presentation

Fluoro complex formation of Rf and Db

Nagame, Yuichiro; Akiyama, Kazuhiko*; Asai, Masato; Goto, Shinichi*; Haba, Hiromitsu*; Ishii, Yasuo; Kasamatsu, Yoshitaka; Nishinaka, Ichiro; Sato, Tetsuya; Tome, Hayato*; et al.

no journal, , 

We present a study of fluoro complex formation of the transactinide elements, rutherfordium (Rf) and dubnium (Db), at JAEA (Japan Atomic Energy Agency). The transactinide nuclides $$^{261}$$Rf and $$^{262}$$Db were produced in the reactions $$^{248}$$Cm($$^{18}$$O,5n) and $$^{248}$$Cm($$^{19}$$F,5n), respectively, at the JAEA tandem accelerator. Ion-exchange behavior of Rf and Db together with their lighter homologues in HF/HNO$$_{3}$$ mixed solutions has been investigated with a rapid ion-exchange separation apparatus AIDA. It has been found that fluoro complexation of Rf is significantly different from that of the homologues. A large difference in the adsorption behavior of Db and the homologue Ta on the anion-exchange resin has been also observed.

Oral presentation

Sequential separation of ultra-trace U, Th, Pb, and lanthanides with a single anion-exchange column

Miyamoto, Yutaka; Yasuda, Kenichiro; Magara, Masaaki; Kimura, Takaumi

no journal, , 

A simple automatic system for sequential separation of U, Th, Pb, and the lanthanides using a single anion-exchange column was developed. The system consists of a tiny anion-exchange column, switching valves controlled by a PC, and a gas bottle to pressurize the eluents. The separation of elements of interest was optimized for several parameters including particle size, column length, and flow rate of eluents. The elements of interest were completely separated within 6 hours by use of this system.

Oral presentation

Aqueous-phase chemistry of the heaviest elements

Nagame, Yuichiro

no journal, , 

Oral presentation

A Preliminary study of prompt $$gamma$$-ray activation analysis using pulsed neutron at J-PARC/ANNRI

Toh, Yosuke; Harada, Hideo; Kimura, Atsushi; Nakamura, Shoji; Furutaka, Kazuyoshi; Kitatani, Fumito; Hara, Kaoru; Koizumi, Mitsuo; Ebihara, Mitsuru*

no journal, , 

The Accurate Neutron-Nucleus Reaction Measurement Instrument (ANNRI) has been constructed at the beamline No.04 at the Material and Life Science Experimental Facility (MLF) of the Japan Proton Accelerator Research Complex (J-PARC). ANNRI has been used for the measurement of nuclear cross-section data, nuclear astrophysics and prompt $$gamma$$-ray analysis (PGA). We have developed a time-of-flight prompt $$gamma$$-ray analysis combined with $$gamma$$-ray coincidence technique. This method will be improved a signal to noise ratio. Preliminary experiments of standard reference materials were made in ANNRI. In this study, the background spectra, the data acquisition dead time and the effect of the self-shield of neutron flux have been measured and evaluated.

Oral presentation

Nuclear and radiochemical study of production and utilization of radioactive astatine isotopes in the Li + $$^{nat}$$Pb reaction

Nishinaka, Ichiro; Yokoyama, Akihiko*; Washiyama, Koshin*; Amano, Ryohei*; Maeda, Eita*; Yamada, Norihiro*; Makii, Hiroyuki; Watanabe, Shigeki; Ishioka, Noriko; Hashimoto, Kazuyuki

no journal, , 

Oral presentation

Redox studies of the heaviest elements using an electrolytic column apparatus

Toyoshima, Atsushi; Oe, Kazuhiro; Asai, Masato; Miyashita, Sunao; Sato, Tetsuya; Sato, Nozomi; Kaneya, Yusuke*; Kitatsuji, Yoshihiro; Tsukada, Kazuaki; Nagame, Yuichiro; et al.

no journal, , 

Oral presentation

Extraction behavior of Mo(VI), Mo(V), W(VI), and W(V) from HCl solutions by Aliquat 336

Yokokita, Takuya*; Oe, Kazuhiro; Komori, Yukiko*; Kikutani, Yuki*; Kino, Aiko*; Nakamura, Kohei*; Kasamatsu, Yoshitaka*; Takahashi, Naruto*; Yoshimura, Takashi*; Takamiya, Koichi*; et al.

no journal, , 

We carried out solvent extraction of Mo(VI), Mo(V), W(VI) and W(V) in 0.01-0.36 M Aliquat 336 / 0.1-11 M HCl system as model experiments for element 106, seaborgium (Sg). The HCl solutions of Mo(VI), Mo(V), W(VI) and W(V) were prepared using macro amounts of Mo and W. Extraction behaviors of mononuclear Mo and W were also investigated using carrier-free radiotracers $$^{99}$$Mo and $$^{181}$$W, which were produced as $$^{235}$$U(n, f) and $$^{181}$$Ta (p, n) reaction, respectively. The distribution ratios (D) of Mo(V) and W(V) were higher than those of Mo(VI) and W(VI), respectively. These results suggest that reduction behavior of the group-6 elements can be observed by solvent extraction. The D values of carrier-free Mo(VI) and W(VI) are almost the same as those with macro amounts in 6-11 M HCl. This condition would be suitable for the Sg experiments.

Oral presentation

Isotopic composition of uranium in aerosol samples collected at 120 km south-southwestern of Fukushima before and after the nuclear power plant accident

Shinonaga, Taeko*; Markus, L.*; Okura, Takehisa

no journal, , 

The isotopic composition of uranium (U) in aerosol samples collected before and after the accident of the Fukushima Daiichi Nuclear Power Plant (FDI-NPP), occurred on March 11, 2011, was studied. The aerosol samples were collected on filters by an air sampling system in Tokai, Japan (at 120 km south-southwestern of the FDI-NPP). The U isotopic composition in each filter was analyzed by sector field inductively coupled plasma mass spectrometry (SF-ICPMS). The compositions of U in the samples collected after the accident show that non-natural U existed in the aerosol. The results of series measurements of radioactive materials before and after the accident indicate that the radioactive materials released from the FDI-NPP into the atmosphere were transported to the sampling station in Tokai, a place at 120 km distance from the FDI-NPP, within a day.

Oral presentation

Liquid-phase studies of seaborgium using the automated liquid-liquid extraction system SISAK

Omtvedt, J. P.*; Oe, Kazuhiro; Lerum, H. V.*; Toyoshima, Atsushi; Haba, Hiromitsu*; Tsukada, Kazuaki; Kratz, J. V.*; Nagame, Yuichiro; Sch$"a$del, M.

no journal, , 

We are planning to investigate the redox potentials of element 106, seaborgium, with a combination of the automated liquid-liquid extraction system SISAK and a flow electrolytic column. In order to combine these two apparatuses, we need to reduce the liquid flow-rate of the SISAK system. In this study, a new degasser, which works with a lower flow rate, was developed for SISAK. It separates the gas-liquid mixture using a hydrophobic Teflon membrane (only the gas can go through the membrane). Using this new degasser, dissolution efficiencies of gas-jet transported products were measured. A high yield of around 80% was observed at a flow rate of 0.1 mL/s with a mixer for the gas-liquid mixing. This result has never been achieved with the conventional SISAK degasser. This is an important step forward with respect to combining the SISAK system with a flow electrolytic column for performing redox experiments on Sg.

Oral presentation

Development of decontamination technology using ionic liquid as a medium for treating waste contaminated with uranium

Ohashi, Yusuke

no journal, , 

In this study we estimated the applicability of process using BMICl and chorin chloride-urea ionic liquid (CCU) for metal waste and NaF waste contaminated with uranium. Dissolution experiments were carried out by adding UF$$_{4}$$ samples in BMICl and CCU in air. UF$$_{4}$$ samples were completely dissolved in BMICl after around 6h at 100$$^{circ}$$C. 38% samples were also dissolved in CCU after 5h at 100$$^{circ}$$C. 86% of uranium in Sodium fluoride (NaF) waste was also dissolved in BMICl after 3h at 100$$^{circ}$$C in air. 64% of uranium in NaF also dissolved in CCU after 3h at 100$$^{circ}$$C. Cyclic voltammograms of the sample solutions prepared by dissolving steel waste into BMICl were measured. The result suggests that electrolytic deposit of iron could not get mixed in with uranium deposit.

Oral presentation

Nondestructive analysis of difficult-to-measure radionuclides by TOF-PGA

Toh, Yosuke; Ebihara, Mitsuru*; Huang, M.; Kimura, Atsushi; Nakamura, Shoji; Harada, Hideo

no journal, , 

Oral presentation

Determination of Zr and Mo isotopes in spent nuclear fuel solution by isotope dilution inductively coupled plasma mass spectrometry for validation of calculated values

Asai, Shiho; Hanzawa, Yukiko; Konda, Miki; Suzuki, Daisuke; Magara, Masaaki; Kimura, Takaumi

no journal, , 

Isotopes of Zr and Mo including both radio and stable isotopes can be found in spent nuclear fuel. Of these isotopes, $$^{93}$$Zr and $$^{93}$$Mo which have long half-lives of 1.61 $$times$$ 10$$^{6}$$ y and 4 $$times$$ 10$$^{3}$$ y, respectively, are of great importance from the viewpoint of managing high-level radioactive wastes in a long-term basis. In this study, contents of Zr and Mo isotopes in spent nuclear fuel solution were determined by isotope dilution inductively coupled plasma mass spectrometry. The sample solution was prepared by dissolving a Japanese PWR irradiated UO$$_{2}$$ fuel with a burnup of 51 GWd/t. The measured contents of $$^{90}$$Zr, $$^{91}$$Zr, $$^{92}$$Zr, $$^{93}$$Zr, $$^{94}$$Zr, and $$^{96}$$Zr in the sample were agreed well with the predicted values obtained through a burnup calculation code ORIGEN2. For Mo, the contents in the sample were approximately 30% less than the predicted values, indicating that part of Mo exists in the insoluble residue.

24 (Records 1-20 displayed on this page)