Search Results - "Usuda, Shigekazu"
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Chromatographic Separation Behaviors of Am, Cm, and Eu onto TODGA and DOODA(C8) Adsorbents with Hydrophilic Ligand–Nitric Acid Eluents
Published in Chemistry letters (05-10-2013)“…Mutual separation behaviors of trivalent minor actinoids (Am and Cm) were examined using not only 241Am and 243Cm but also 152Eu for comparison with behaviors…”
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Evaluation study on properties of isohexyl-BTP/SiO2-P resin for direct separation of trivalent minor actinides from HLLW
Published in Journal of radioanalytical and nuclear chemistry (01-05-2012)“…In order to develop a direct separation process for trivalent minor actinides from fission products in high level liquid waste (HLLW) by extraction…”
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An advanced partitioning process for key elements separation from high level liquid waste
Published in Science China. Chemistry (01-09-2012)“…To separate MA (Am, Cm) and some fission product elements (FPs) such as Tc, Pd, Cs and Sr from high level liquid waste (HLLW) systematically, we have been…”
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Adsorption behavior of trivalent americium and rare earth ions onto a macroporous silica-based isobutyl-BTP/SiO2-P adsorbent in nitric acid solution
Published in Journal of radioanalytical and nuclear chemistry (01-01-2014)“…To separate minor actinides from high level liquid waste (HLLW) of PUREX reprocessing, a silica-based macroporous iso butyl-BTP/SiO 2 -P adsorbent was…”
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Adsorption and desorption behavior of tetravalent zirconium onto a silica-based macroporous TODGA adsorbent in HNO3 solution
Published in Journal of radioanalytical and nuclear chemistry (01-07-2013)“…To understand the separation behavior of Zr(IV) in the partitioning process for high level liquid waste, a silica-based macroporous adsorbent (TODGA/SiO 2 -P)…”
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Development of a simplified separation process of trivalent minor actinides from fission products using novel R-BTP/SiO2-P adsorbents
Published in Journal of nuclear science and technology (01-03-2012)“…From a viewpoint of direct separation of trivalent minor actinides (MA: Am, Cm etc.) from fission products (FP) including rare earths (RE) in high level…”
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Application of Inductively Coupled Plasma Mass Spectrometry to the determination of uranium isotope ratios in individual particles for nuclear safeguards
Published in Spectrochimica acta. Part B: Atomic spectroscopy (01-10-2007)“…The capability of inductively coupled plasma mass spectrometry (ICP-MS) for the determination of uranium isotope ratios in individual particles was determined…”
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Efficient Isotope Ratio Analysis of Uranium Particles in Swipe Samples by Total-Reflection X-ray Fluorescence Spectrometry and Secondary Ion Mass Spectrometry
Published in Journal of nuclear science and technology (01-11-2004)“…A new particle recovery method and a sensitive screening method were developed for subsequent isotope ratio analysis of uranium particles in safeguards swipe…”
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Numerical Consideration for Multiscale Statistical Process Control Method Applied to Nuclear Material Accountancy
Published in Journal of nuclear science and technology (01-10-2006)“…The multiscale statistical process control (MSSPC) method is applied to clarify the elements of material unaccounted for (MUF) in large scale reprocessing…”
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Application of Fission Track Technique for the Analysis of Individual Particles Containing Uranium in Safeguard Swipe Samples
Published in Japanese Journal of Applied Physics (01-07-2004)“…An effective method for isotope ratio analysis of individual particles containing uranium in safeguard swipe samples was developed by using a fission track…”
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A Screening Method for Uranium Particles in Safeguards Environmental Samples Based on Etching Behavior of Fission Tracks
Published in Japanese Journal of Applied Physics (01-11-2006)Get full text
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Applicability of insoluble tannin to treatment of waste containing americium
Published in Journal of alloys and compounds (12-06-1998)“…The applicability of insoluble tannin adsorbent to the treatment of aqueous waste contaminated with americium has been investigated. Insoluble tannin is…”
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Challenge to ultra-trace analytical techniques of nuclear materials in environmental samples for safeguards at JAERI: methodologies for physical and chemical form estimation
Published in International journal of environmental analytical chemistry (10-08-2006)“…From a viewpoint of physical and chemical form estimation, ultra-trace analytical techniques of nuclear materials in environmental samples for safeguards have…”
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Properties of a YAP powder scintillator as alpha-ray detector
Published in Applied radiation and isotopes (01-03-2000)“…A YAP scintillator (YAlO 3: Ce crystal) for α counting has been produced in powder form and this paper describes its performance characteristics. By measuring…”
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Separation of Am and Cm by using TODGA and DOODA(C8) adsorbents with hydrophilic ligand-nitric acid solution
Published in Journal of radioanalytical and nuclear chemistry (01-02-2015)“…Extraction chromatographic separation of trivalent minor actinides (MA: Am and Cm) was investigated by using solid adsorbents impregnating the lipophilic…”
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Adsorption behavior of trivalent americium and rare earth ions onto a macroporous silica-based /sobutyl- BTF/Si[O.sub.2]-P adsorbent in nitric acid solution
Published in Journal of radioanalytical and nuclear chemistry (01-01-2014)“…To separate minor actinides from high level liquid waste (HLLW) of PUREX reprocessing, a silicabased macroporous isobutyl-BTP/Si[O.sub.2]-P adsorbent was…”
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Adsorption and desorption behavior of tetravalent zirconium onto a silica-based macroporous TODGA adsorbent in HN[O.sub.3] solution
Published in Journal of radioanalytical and nuclear chemistry (01-07-2013)“…To understand the separation behavior of Zr(IV) in the partitioning process for high level liquid waste, a silica-based macroporous adsorbent…”
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Adsorption Characteristics of Trivalent Rare Earths and Chemical Stability of a Silica-Based Macroporous TODGA Adsorbent in HNO3 Solution
Published in Journal of nuclear science and technology (01-09-2011)“…In order to separate trivalent minor actinides (Am and Cm) from high-level liquid waste generated in a nuclear fuel reprocessing process, a silica-based…”
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