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Journal Articles

Continuous liquid-liquid extraction of uranium from uranium-containing wastewater using an organic phase-refining-type emulsion flow extractor

Nagano, Tetsushi; Naganawa, Hirochika; Suzuki, Hideya; Toshimitsu, Masaaki*; Mitamura, Hisayoshi*; Yanase, Nobuyuki*; Grambow, B.

Analytical Sciences, 34(9), p.1099 - 1102, 2018/09

 Times Cited Count:6 Percentile:45.81(Chemistry, Analytical)

A previously reported emulsion flow (EF) extraction system does not include a device for refining used solvent. Therefore, the processing of large quantities of wastewater by using the EF extractor alone could lead to the accumulation of wastewater components into the solvent and diminished extraction performance. In the present study, we have developed a solvent-washing-type EF system, which is equipped with a unit for washing used solvent to prevent accumulation, and successfully applied it for treating uranium-containing wastewater.

Journal Articles

Isotope dilution inductively coupled plasma mass spectrometry for determination of $$^{126}$$Sn content in spent nuclear fuel sample

Asai, Shiho; Toshimitsu, Masaaki; Hanzawa, Yukiko; Suzuki, Hideya; Shinohara, Nobuo; Inagawa, Jun; Okumura, Keisuke; Hotoku, Shinobu; Kimura, Takaumi; Suzuki, Kensuke*; et al.

Journal of Nuclear Science and Technology, 50(6), p.556 - 562, 2013/06

 Times Cited Count:7 Percentile:41.73(Nuclear Science & Technology)

The $$^{126}$$Sn content in a spent nuclear fuel solution was determined by ICP-MS for its inventory estimation in high-level radioactive waste. An irradiated UO$$_{2}$$ fuel was used as a sample to evaluate the reliability of the methodology. Prior to the measurement, Sn was separated from $$^{126}$$Te, which causes major isobaric interference in the determination of $$^{126}$$Sn content, along with highly radioactive coexisting elements using an anion-exchange column. The absence of counts attributed to Te in the Sn-containing effluent indicates that Te was completely removed. After washing, Sn retained on the column was readily eluted with 1 M HNO$$_{3}$$. The isotope ratios of Sn were successfully determined and showed good agreement with those obtained through ORIGEN2 calculations. The results reported in this paper are the first experimental values of $$^{126}$$Sn content in the spent nuclear fuel solution originating in spent nuclear fuel irradiated at a nuclear power plant in Japan.

Journal Articles

Simple cation-exchange separation for ICP-MS measurement of $$^{79}$$Se in spent nuclear fuel sample

Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Inagawa, Jun; Suzuki, Kensuke*; Kaneko, Satoru*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Journal Articles

New ORIGEN2 libraries based on JENDL-4.0 and their validation for long-lived fission products by post irradiation examination analyses of LWR spent fuels

Kojima, Kensuke; Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Okamoto, Tsutomu; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Accurate inventory estimation of long-lived fission products (LLFPs) in LWR spent fuels is important for the quality management and for long-term safety assessment of high-level radioactive vitrified wastes. In Japan, ORIGEN2 has been widely used to estimate the fuel compositions. However, equipped library data in the original ORIGEN2 are old and are not validated enough for LLFPs, such as $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs, because available post irradiation examination (PIE) data are limited for these nuclides, which have difficulties in radiochemical analyses. For more accurate the estimation, new ORIGEN2 libraries are developed from the latest nuclear data library JENDL-4.0 for cross sections and fission yields, and from other libraries for half-lives, and so on. The new libraries are validated by PIE analyses of the sample fuels irradiated in Cooper, Calvert-Cliffs-1, H. B. Robinson-2, and Ohi-1. As a result, it was found that the new library gives good results for the estimation.

Journal Articles

Analyses of assay data of LWR spent nuclear fuels with a continuous-energy Monte Carlo code MVP and JENDL-4.0 for inventory estimation of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Okamoto, Tsutomu; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Progress in Nuclear Science and Technology (Internet), 2, p.369 - 374, 2011/10

For accurate inventory estimation of long-lived fission products in LWR spent fuels, a new burn-up chain model and decay data based on the latest nuclear data such as JENDL-4.0 was developed. MVP-BURN with the latest nuclear data was applied to several post irradiation examinations including inventory measurements of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs. One of them is a new measurement by JAEA. From the PIE analyses, it is found that the new PIE data obtained by JAEA is consistent with the other PIE data by different laboratory with different techniques. It is also confirmed that the present calculation results show good agreements with experimental ones within about 10% for productions of $$^{79}$$Se and $$^{135}$$Cs. In contrast, amounts of $$^{99}$$Tc and $$^{126}$$Sn are overestimated by about 50%. These discrepancies are likely due to the effect of insoluble residue produced during sample dissolution and/or errors of fission yields in the analyses.

Journal Articles

Validation of correlations between Nd isotopes and difficult-to-measure nuclides predicted with burn-up calculation code by post irradiation examination

Asai, Shiho; Okumura, Keisuke; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of 14th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2011) (CD-ROM), p.1437 - 1442, 2011/09

Journal Articles

Computational study for inventory estimation of Se-79, Tc-99, Sn-126, and Cs-135 in high-level radioactive wastes from spent nuclear fuels of light water reactors

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Okamoto, Tsutomu; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Suzuki, Kensuke*; Kaneko, Satoru*

Proceedings of 14th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2011) (CD-ROM), p.1443 - 1450, 2011/09

Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction, power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible ranges of generations. Finally, candidates of the key nuclide are proposed for the scaling factor method of HLW.

Journal Articles

Comparison of post-irradiation experimental data and theoretical calculations for inventory estimation of long-lived fission products in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Suzuki, Hideya; Toshimitsu, Masaaki; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.261 - 264, 2010/10

Journal Articles

Post irradiation examination analyses with a continuous-energy Monte Carlo code MVP for long-lived fission products in LWR spent fuels

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Katakura, Junichi; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive), 5 Pages, 2010/10

For accurate inventory estimation of long-lived fission products in LWR spent fuels, a new burn-up chain model and decay data based on the latest nuclear data were developed for MVP-BURN. They were applied to three post irradiation examinations including inventory measurements of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs. One of them is new measurements performed by JAEA. From the PIE analyses, it is found that the new measurements by JAEA are consistent with the other PIE data obtained by different laboratory with different techniques. It is also confirmed that the present calculation results show good agreements with experimental ones for $$^{79}$$Se and $$^{135}$$Cs within about 10%. In contrast, amounts of $$^{99}$$Tc and $$^{126}$$Sn are overestimated by about up to 50%. These discrepancies are likely due to the effect of insoluble residue in the measurements and/or errors of fission yields in the analyses.

Oral presentation

Determination of long-lived radionuclide in spent nuclear fuel; Simple and rapid sample preparation for determination of $$^{79}$$Se

Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

no journal, , 

no abstracts in English

Oral presentation

Determination of long-lived radionuclide in spent nuclear fuel; Anion-exchange separation of tin for $$^{126}$$Sn determination

Toshimitsu, Masaaki; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Inagawa, Jun; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

no journal, , 

no abstracts in English

Oral presentation

Study on recovery of useful elements from simulated radioactive liquid waste by photo-reduction

Saeki, Morihisa; Toshimitsu, Masaaki; Oba, Hironori

no journal, , 

no abstracts in English

Oral presentation

Study on recovery of useful elements from simulated radioactive liquid waste by photo-reduction

Oba, Hironori; Saeki, Morihisa; Toshimitsu, Masaaki

no journal, , 

The recovery characteristics of useful elements such as platinum group metals from a simulated radioactive solution by photo-reduction using an UV-vis light were experimentally examined. A 10-components simulated solution was prepared by dissolving known amounts of metallic compounds (Ru, Rh, Pd, Mo, Zr, Ba, Sr, Cs, Nd) and sodium in nitric acid of 3 mol/l. The metallic palladium was selectively recovered from the simulated solution containing TiO$$_{2}$$-photocatalyst, while other elements mainly remained in solution. The recovery efficiency of Pd increased with the increase of the TiO$$_{2}$$ concentration and was more than 99% at a TiO$$_{2}$$ concentration above 2 g/l.

Oral presentation

Analysis of elements in aqueous solution using laser-induced breakdown spectroscopy

Oba, Hironori; Toshimitsu, Masaaki; Saeki, Morihisa; Tanabe, Rie*; Ito, Yoshiro*; Wakaida, Ikuo

no journal, , 

no abstracts in English

Oral presentation

High sensitive analysis of elements in aqueous solution by using laser-induced breakdown spectroscopy

Oba, Hironori; Toshimitsu, Masaaki; Saeki, Morihisa; Tanabe, Rie*; Ito, Yoshiro*; Wakaida, Ikuo

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

Development of in-vessel inspection technology using remote imaging and spectroscopy, 2; Development of laser-induced breakdown spectroscopy technique for solid samples submerged in water

Toshimitsu, Masaaki; Saeki, Morihisa; Sugiyama, Akira; Oba, Hironori; Thornton, B.*; Sakka, Tetsuo*

no journal, , 

no abstracts in English

Oral presentation

Selective separation of refractory and platinum-group metals from a simulated solution of radioactive waste by titanium oxide particles

Saeki, Morihisa; Toshimitsu, Masaaki; Oba, Hironori

no journal, , 

One ton of high-level radioactive waste (HLRW) that is generated from nuclear power plant contains a few kilograms of refractory and platinum-group metals, such as Mo, Zr and Pd. Separation of refractory and platinum-group metals from HLRW contributes to smooth operation of vitrification process. On the other hand, titanium oxide materials adsorb metals by ion-exchange function and micronize metals by photocatalyst function. In this work, we attempted to separate the refractory and platinum-group metals from simulated solution of HLRW by using the titanium oxide nanoparticles, and investigate dependence of recovery efficiency on the particle size.

Oral presentation

Development of remote laser-induced breakdown spectroscopy for samples submerged in water

Toshimitsu, Masaaki; Saeki, Morihisa; Oba, Hironori; Thornton, B.*; Sakka, Tetsuo*

no journal, , 

A laser-induced breakdown spectroscopy (LIBS) technique for element analysis of samples submerged in water using a fiber optic light delivery set-up has been developed. The set-up delivers air to the sample surface via a tube and uses the same fiber optic for laser light delivery, and for observation of the light emitted by the micro-plasma generated for analysis. The emission spectra from metals, alloys and oxide samples such as Fe, SUS304, zircaloy-2, ZrO$$_{2}$$ can be clearly observed at wavelengths ranging from 730 nm to 870 nm.

Oral presentation

Study on separation of platinum-group metals by using laser-induced particle formation

Saeki, Morihisa; Toshimitsu, Masaaki; Oba, Hironori

no journal, , 

We proposed separation technique of platinum-group metals (PGMs) from a solution of high-level radioactive waste by using laser-induced particle formation, and performed its proof-of-principle experiment. The simulated solution of high-level radioactive liquid wastes (HLLW) was prepared by dissolving Pd, Rh, Ru and neodymium (Nd) into distilled water. The Nd metal was added as representative of lanthanide and minor actinide. After 40-min irradiation of an UV laser to mixture of the simulated solution of HLLW and ethanol, the Pd, Rh and Ru metals were separated from the Nd ion as particle with sub-micron size. The Pd, Rh and Ru metals were recovered with efficiency of 100%, 94-99%, 65-69%, while the Nd ion was completely kept in the sample solution. Moreover, we investigated dependence of recovery efficiency on various experimental parameters. The results suggest mutual separation of Pd and Rh by arrangement of the intensity of the irradiation laser.

28 (Records 1-20 displayed on this page)