Updated on 2021/11/12

写真a

 
ENOKIDA, Youichi
 
Organization
Graduate School of Engineering Applied Energy 2 Professor
Graduate School
Graduate School of Engineering
Undergraduate School
School of Engineering Energy Science and Engineering
Title
Professor

Degree 1

  1. Dr. Eng. ( The University of Tokyo ) 

Research Interests 8

  1. 放射性廃棄物処理,技術コミニュケーション

  2. 同位体分離工学

  3. 超臨界流体

  4. アクチニドの科学

  5. 分離工学

  6. 核燃料サイクル工学

  7. 原子力化学工学

  8. 原子力工学

Research Areas 3

  1. Others / Others  / Nuclear Fuel Cycle Engineering

  2. Others / Others  / Nuclear Chemical Engineering

  3. Others / Others  / Nuclear Engineering

Current Research Project and SDGs 6

  1. Utilization of Nuclear Energy with the minimum radioactive waste

  2. professional and technical communication on nuclear technology

  3. Science and Engineering for Nuclear Fuel Reprocessing

  4. Advanced Recycle Engineering for Nuclear Fuels

  5. Engineering for Actinide Separation

  6. Management of Used Nuclear Fuel

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Research History 14

  1. Nagoya University   Nuclear Materials Management Facility

    2016.4 - 2018.3

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    Country:Japan

  2. Nagoya University   Nuclear Materials Management Facility   Director

    2009.4 - 2011.3

  3. Division Director, Division fo Environmental Research, EcoTopia Science Institute, Nagoya University

    2006.4 - 2008.3

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    Country:Japan

  4. Professor, EcoTopia Science Institute, Nagoya University

    2005.4 - 2011.3

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    Country:Japan

  5. Director of Nuclear Materials Management Fcility, Nagoya University

    2005.4 - 2007.3

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    Country:Japan

  6. Professor, EcoTopia Science Institute, Nagoya University

    2004.4 - 2005.3

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    Country:Japan

  7. Professor, Research Center for Nuclear Materials Recycle, Nagoya University

    2001.4 - 2004.3

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    Country:Japan

  8. Associate Professor, Department of Materials Science and Engineering, Graduate School of Engineering

    1997.4 - 2001.3

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    Country:Japan

  9. Associate Professor, Department of NUclear ENgineering, School of Engineering, Nagoya UNiversity

    1996.9 - 1997.3

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    Country:Japan

  10. Mitsubishi Heavy Industries and Mitsubishi Atomic Power Industries

    1993.8 - 1996.8

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    Country:Japan

  11. Visiting Professor, Oak Ridge National Laboratory, United Ststes of America

    1990.4 - 1991.3

  12. Associate Professor, Department of Nuclear Engineering, Faculty of Engineering, the University of Tokyo

    1989.6 - 1993.7

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    Country:Japan

  13. Lecturer, Department of Nuclear Engineering, Fuculty of Engineering, the University of Tokyo

    1987.8 - 1989.5

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    Country:Japan

  14. Research Associates, Department of Nuclear Engineering, Fuculty of Engineering, the University of Tokyo

    1984.4 - 1987.7

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    Country:Japan

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Education 2

  1. The University of Tokyo   Graduate School, Division of Engineering   Department of Nuclear Engineering

    - 1983

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    Country: Japan

  2. The University of Tokyo   Faculty of Engineering   Department of Nuclear Engineering

    - 1981

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    Country: Japan

Professional Memberships 5

  1. American Nuclear Society

  2. American Chemical Society

  3. The Atomic Energy Society of Japan

  4. 日本化学会

  5. The Japan Society of Nuclear and Radiochemical Sciences

Committee Memberships 2

  1. Nuclear Regulatory Agency   Member of Nuclear Fuel Safety Committee  

    2016.11   

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    Committee type:Government

  2. Nuclear Energy System Symposium   Chairman  

    2013.5   

Awards 3

  1. Albert Nelson Marquis Lifetime Achievement Award 2020

    2020.12   Albert Nelson Marquis & Company  

  2. 2019 Albert Nelson Marquis Lifetime Achievement Award

    2018.12   Albert Nelson Marquis   2019 Albert Nelson Marquis Lifetime Achievement Award

    Youichi Enokida

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    Award type:Award from publisher, newspaper, foundation, etc.  Country:United States

  3. The Albert Nelson Marquis Lifetime Achievement Award

    2017.12   New Communication company  

    Youichi Enokida

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    Award type:International academic award (Japan or overseas)  Country:United States

 

Papers 223

  1. Observation of nepheline crystallization in the Na2O-B2O3-Al2O3-SiO2 system for the vitrification of zeolites absorbing Cs

    澤田佳代, 榎田洋一

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY     2021.9

  2. Oxidation and vitrification of aluminum with lead borate glass for low level radioactive waste treatment

    Sawada Kayo, Enokida Youichi, Tsukada Takeshi

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 57 ( 6 ) page: 671 - 677   2020.6

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  3. Kinetics of chlorination of uranium-antimony composite oxide for uranium removal from waste catalyst used for acrylonitrile synthesis Reviewed

    Sawada Kayo, Hirabayashi Daisuke, Enokida Youichi

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 56 ( 4 ) page: 317 - 321   2019.4

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    Language:Japanese   Publishing type:Research paper (scientific journal)  

    Kinetics of chlorination of uranium-antimony composite oxide was investigated for uranium removal from waste catalyst used for acrylonitrile synthesis. reaction rate is evaluated experimentally and rate constant is determined.

    DOI: 10.1080/00223131.2019.1580622

    Web of Science

  4. Revisit of Phase Separation of Borosilicate Glass for Vitrification of High Level Radioactive Waste Reviewed

    Youichi Enokida, Seo Uchimura, Kayo Sawada

    Proceedings of Waste Management Symposia 2019   Vol. CR-ROM ( 19166 ) page: 1-4   2019.3

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    Phase separation of glasses for vitrification of high level radioactive waste has been experimentally studied to know uncertainty of the phase separation conditions; temperature and glass compositions as well as to propose possibility of recycling of heavy metals on a longer time scale. Our current results at 700 and 750 ℃ for ternary borosilicate glass system showed that the phase separation region at 700 ℃ spreads along with a direction of increasing Na2O composition when compared with the data in literature. On the other hand, at the glass composition employed in the reprocessing plant in Japan, no segregation was observed. Concerning the application of phase separation phenomena, we had previously reported recovery of almost all elements from the vitrified borosilicate glass containing simulated fission products through phase separation of the borosilicate glass and this suggests that we could propose that after vitrification of high-level radioactive waste heavy metals may be retrieved as energy or materials resources when they are required to utilize on a longer time scale. From this standpoint, phase separation of lead borosilicate glass was also studied to seek economical and versatile recycling.

  5. 理事会で議論されていること Invited

    榎田洋一

    日本原子力学会誌   Vol. 59 ( 2 ) page: 109   2017.2

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    日本原子力学会理事会報告

  6. Ruthenium release from thermally overheated nitric acid solution containing ruthenium nitrosyl nitrate and sodium nitrate to solidify Reviewed

    Kayo Sawada, Yasuyuki Ueda, Youichi Enokida

    Procedia Chemistry   Vol. 21   page: 82-86   2016.12

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    DOI: 10.1016/j.proche.2016.10.012

  7. Proposal and Feasibility of Liquid-Liquid Extraction with Polyethylene Glycol for Partitioning of Molybdenum and Ruthenium Reviewed

    Youichi Enokida, Shota Daibo, Takahiko Sugiyama, and Kayo Sawada

      Vol. CD-ROM   page: 1547-1553   2015.9

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    The Science Council of Japan (SCJ) has issued recommendations to Japan Atomic Energy Commission on the advanced management of high-level radioactive wastes (HLW) in Japan. One of the SCJ's recommendations has included a proposal of an extended storage by the moratorium before the first deep geological disposal of the HLW from the reprocessing of the thermal nuclear reactors so as to cultivate advanced technological options for partitioning and transmutation or deep geological disposal. In this context, the current paper would propose partitioning of ruthenium (Ru) and molybdenum (Mo) from the HLW at a reprocessing plant for used fuels from the thermal nuclear reactors to warrant performance of vitrification by the liquid fed ceramic melter technology by removing Ru and safety confinement of the vitrified glass by removing Mo.
    In order to minimize generating the secondary waste from the actual processes employed for the partitioning, liquid-liquid extraction with using no organophosphorus compound but with polyethylene glycol (PEG) was tested in this study in a laboratory scale.
    The liquid-liquid extraction systems using PEG have been historically developed for partitioning of pertechnetate since the seminal work by D. Rogers USA in this several decades.
    In this paper, we would report not only distribution ratios of Ru and Mo in a biphasic system of 40% aqueous solution of PEG of which molecular weight was 2x103 and 2 molar aqueous solution of sodium carbonate, a new salting effect by carbonate ions on metal species which could experimentally enhance the distribution of perrhenate by a factor of more than 10, and found to be partially substitutable by high pressure carbon dioxide for an addition of metallic carbonate salt which may lead to further minimization of the secondary waste.
    From a standpoint of continuous operation of liquid-liquid extractor such as a mixer-settler, a pulsed column, and a centrifugal contactor, time constants of coalescence of dispersed droplets in aqueous continuous (PEG-in-aqueous; P/A) and organic continuous operations (Aqueous-in-PEG; A/P) were experimentally evaluated to be 9.9 and 9.1 seconds respectively, which implies both modes would be probable, but PEG phase would be appropriate as a continuous one for the operation. Additionally, the observed averaged diameters of the dispersed phases at P/A and A/P operations were 0.26±0.03 and 3.5±0.04 mm, respectively. The initial formation of droplets at the tube outlet was well predicted by the empirical equation with using experimentally measured values of surface tension (2.4×10-4 Nm-1) and density difference (3.9×101 kg m-3) for the system.
    Overall mass transfer coefficients were experimentally evaluated by applying a single droplet method for A/P operation mode in a laboratory scale and the evaluated values ranged 3 through 9×10-8 m s-1. These values are smaller than those for uranium in the Purex solvent extraction system by the two order of magnitude, then mass transfer enhancement is one of the future technical tasks for this system for the actual implementation

  8. Effect of the Glass Structure on the Leachability of Borosilicate Glass for HLW Vitrification Reviewed

    Kayo Sawada, Yuki Ota, Koji Fujii, Takahiko Sugiyama, Youichi Enokida

    Proceedings of Global 2015   Vol. CD-ROM   page: 1441-1445   2015.9

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    The leachability of each series of the borosilicate glass having a constant molar ratio of silicon dioxide and boron trioxide, K, showed similar tendency in three series of the samples composed of three components of boron trioxide, silicon dioxide and sodium oxide, whose values of K were 3.0, 3.7 and 4.2, employed in this study. The initial leaching rate decreased with an increase of the molar ratio of sodium oxide to boron trioxide, R, to Rmax defined as (1/2 + K/16) in the Dell model for the borate structure in borosilicate glass, and then increased with an increase of R from Rmax. The leachability of borocilicate glass seemed low when it was governed to be reedmergnerite structure.

  9. Leaching Rate of the Borosilicate Glass Containing Molybdenum Oxide Reviewed

    Koji Fujii, Yuki Ota, Kayo Sawada, Takahiko Sugiyama, Youichi Enokida

    Proceedings of Waste Management Symposia 2015   Vol. CD-ROM ( 15546 ) page: 1-7   2015.3

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  10. Supercritical carbon dioxide enhanced extraction of metal ions in an aqueous two-phase system using polyethylene glycol Reviewed

    Y. Enokida, K. Sawada, S. Daibo

    The Proceedings of the 14th European Meeting on Supercritical Fluids   Vol. CD-ROM ( E12 ) page: 1-8   2014.5

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    Liquid-liquid extraction of metal ions in an aqueous two-phase system using aqueous solution of polyethylene glycol and sodium carbonate is experimentally studied to extend applicable metal species from TcO4- to RuO42- and MoO42- for nuclear waste treatment in nuclear energy application, and to MnO4- and CoO2- for recycling of raw materials of lithium ion batteries. Additionally, salting effect of using aqueous carbonate ions is experimentally investigated and use of high pressure carbon dioxide is discussed. As a consequence, the aqueous two-phase system using polyethylene glycol and sodium carbonate solution can be applied to extract not only TcO4- but also other anions of metal oxides for energy applications and high pressure carbon dioxide could be of use for salting.

  11. CONTROLLABILITY OF PLUTONIUM CONCENTRATION FOR FBR FUEL AT A SOLVENT EXTRACTION Reviewed

    Youichi Enokida, Motoki Kitano and Kayo Sawada

    The proceedings of the International Nuclear Fuel Cycle Conference   Vol. CD-ROM   page: 535-538   2013.10

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    Typical Purex solvent extraction systems for the
    reprocessing of spent nuclear fuel have a feed material
    containing dilute, 1% in weight, plutonium, along with
    uranium and fission products. Current reprocessing
    proposals call for no separation of the pure plutonium.
    The work described in this paper studied, by computer
    simulation, the fundamental feasibility of preparing a
    20% concentrated plutonium product solution from the
    1% feed by adjusting only the feed rates and acid
    concentrations of the incoming streams and without the
    addition of redox reagents for the plutonium. A set of
    process design flowsheets has been developed to realize a
    concentrated plutonium solution of a 20% stream from
    the dilute plutonium feed without using redox reagents.

  12. INVESTIGATION OF RUTHENIUM DIOXIDE FORMATION MECHANISMS IN CONTAINMENT GLASS Reviewed

    Kayo Sawada, Sophie Schuller, Takahiro Shimada, Naoki Sako, Youichi Enokida

    The Proceedings of the International Nuclear Fuel Cycle Conference   Vol. CD-ROM   page: 453-459   2013.10

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    Highly-active liquid wastes arising from reprocessing
    of spent uranium oxide fuel are confined in a sodium
    borosilicate glass matrix in France and Japan. The
    complementarity of the scientific and methodological
    approaches developed in the two institutes, CEA, France
    and Nagoya University, Japan had allowed the
    cooperation program to mutually enrich their knowledge
    of the mechanisms of crystal formation of RuO2 and its
    influences in the glass. The research topic will cover
    generic studies not related to a particular melter
    technology, but scientific and fundamental data. The
    presenting paper focuses on the structural configuration of
    ruthenium in vitreous matrices with the objective of
    obtaining more insight into ruthenium incorporation and
    solubilization mechanisms in borosilicate glasses.

  13. Preliminary Evaluation of Cesium Distribution for Wet Sieving Process Planned for Soil Decontamination in Japan Reviewed

    Y. Enokida, Y. Tanada, D. Hirabayashi, K. Sawada

    Proceedings of Waste Management Symposia 2013   Vol. CD-ROM   page: 1-8   2013.2

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    The present study provides scientific data concerning with effectiveness in volume reduction of contaminated soil by the wet sieving process as well as cesium distribution between liquid phase and clay minerals for each sub-process for a full-scale, but simulating plant equipped with a process of coagulating sedimentation and operational safety fundamentals for the plant. Especially for the latter aspect, the study clearly showed that clay minerals of submicron size strongly bounds cesium with high content, and they hardly removed with coagulating with natural sedimentation (1G) nor centrifugal sedimentation (3,700G). By applying ultracentrifugation (257,000G) removed most of submicron clay minerals bounding cesium, and the fraction of cesium may leak to the effluent or recycled water could be reduced to less than 2.3% of the original design by an addition of a cesium barrier consisting of ultracentrifugation or a hollow fiber membrane. The suggestion is based upon reasonable experimental data well coupled with a real plant, and the counter-measure discussed is technologically feasible, which shows the importance of the work.

  14. Reaction of Antimony-Uranium Composite Oxide in the Chlorination Treatment of Waste Catalyst Reviewed

    K. Sawada. D. Hirabayashi, Y. Enokida

    Proceedings of Waste Management Symposia 2013   Vol. CD-ROM   page: 1-8   2013.2

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    The effect of concentration of oxygen gas on the chlorination treatment was investigated by adding different concentrations of oxygen at 0-6 vol% since U3O8 seemed to exist stably when oxygen partial pressure is greater than 0.001 vol% from the potential diagram of the U-H-O system at 1173 K. The higher concentration oxygen became, the lower the conversion was. The effect of oxygen increased with decrease in the concentration of hydrogen chloride gas. When 6 vol% hydrogen chloride gas was used, the addition of oxygen up to 0.1 vol% could convert uranium contained in the catalyst to U3O8 without any remarkable decrease in reaction rate compared with that of the treatment without oxygen.

  15. PREPARATION OF SUPERHYDROPHOBIC PLATINUM CATALYST IN SUPERCRITICAL CARBON DIOXIDE AND ITS PERFORMANCE EVALUATION FOR HYDROGEN ISOTOPE SEPARATION Reviewed

    Y. Enokida, K. Hayashida, T. Suguyama, K. Sawada

    Proceedings of Symposium on Separation Phenomena in Liquids and Gases   Vol. CD-ROM   page: 1-8   2012.12

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  16. Effect of dissolving temperature on the amount of palladium dissolved in borosilicate glass Reviewed

    T. Shimada, K. Sawada, Y. Enokida

    Procedia Chemistry   Vol. 7   page: 604-609   2012.9

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    To clarify the dissolving behavior of palladium, the effect of temperature on the amount of palladium dissolved in borosilicate glass was investigated. Glass and palladium oxide, selected as a starter material, were mixed and heated at prescribed temperature. The amount of dissolved palladium became higher with temperature increasing up to 850 °C, and lower above 850 °C. Above 850 °C, the reduction of palladium oxide was accelerated. For palladium dissolution in borosilicate glass, not only the viscosity and basicity of the glass but also the decomposition temperature of the initial palladium species seemed to affect the amount of palladium dissolved in glass.

    DOI: 10.1016/j.proche.2012.10.092

  17. Low-temperature conversion of spent adsorbent to iodine sodalite by a mechanochemical route Reviewed

    D. Hirabayashi, Y. Tanada, T. Sugiyama, K. Sawada, Y. Enokida

    AIChE Journal   Vol. 58 ( 8 ) page: 2441-2447   2012.8

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    DOI: 10.1002/aic.12756

  18. Lithium isotope separation with displacement chromatography using crown ether resin immobilized on porous silica beads Reviewed

    T. Sugiyama, K. Sugiura, M. Tanaka, Y. Enokida

    Fusion Engineering and Design   Vol. 87 ( 7-8 ) page: 1186-1189   2012.8

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    A crown ether resin immobilized on porous silica beads was investigated as a chromatographic packing for lithium isotope separation by displacement chromatography. In order to develop an effective chromatographic packing, effects of the diameter of the packing particle on the transport phenomena in the particle were investigated by numerical simulation. Transient change of the concentration profiles in the both solution phase and resin phase were obtained and lithium-6 enrichment in the resin phase was well simulated. A dimensionless coefficient, which represents a ratio of the diffusive mass transfer rate to the adsorption rate, was found in the mass balance equation. The magnitude of the factor was also evaluated for various values of diameter of the packing particle. (C) 2012 Elsevier B.V. All rights reserved.

    DOI: 10.1016/j.fusengdes.2012.02.092

  19. Chlorination of antimony and its volatilization treatment of waste antimony-uranium composite oxide catalyst Reviewed

    K. Sawada, and Y. Enokida

    Proceedings of Radiochemistry   Vol. 1 ( 1 ) page: 97-100   2011.9

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    For the waste antimony-uranium composite oxide catalyst, the chlorination of antimony and its volatilization treatment were proposed, and evaluated using hydrogen chloride gas at 873-1173 K. During the treatment, the weight loss of the composite oxide sample, which resulted from the volatilization of antimony, was confirmed. An X-ray diffraction analysis showed that uranium oxide, U3O8, was formed during the reaction. After the treatment at 1173 K for 1 h, almost all the uranium contained in the waste catalyst was
    dissolved by a 3M nitric acid solution at 353 K within 10 min, although that of the non-treated catalyst was less than 0.1%. It was found that the chlorination and volatilization treatment was effective to separate antimony from the composite oxide catalyst and change uranium into its removable form.

    DOI: 10.1524/rcpr.2011.0016

  20. Distribution Coefficients of U(VI), Nitric Acid and FP Elements in Extractions from Concentrated Aqueous Solutions of Nitrates by 30% Tri-n-butylphosphate Solution Reviewed

    Kayo SAWADA, Youichi ENOKIDA, Masayoshi KAMIYA, Tomozo KOYAMA and Kazuo AOKI

    Journal of NUCLEAR SCIENCE and TECHNOLOGY   Vol. 46 ( 1 ) page: 1-7   2009.1

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    The distribution coefficients of uranium, nitric acid and 8 elements simulating FP elements were obtained
    from the concentrated aqueous solutions of nitrates, whose nitrate ion concentrations were 4–
    15 mol/L. The relationships among the distribution coefficient of uranium, the nitrate ion concentration
    in the aqueous phase, and the concentration of tri-n-butylphosphate uncombined with nitrates in the organic
    phase were obtained from the data.

  21. Liquid Metal Extraction for Removal of Molybdenumfrom Molten Glass Containing Simulated Nuclear Waste Elements Reviewed

    Kazuyoshi URUGA, Kayo SAWADA, Youichi ENOKIDA and Ichiro YAMAMOTO

    Journal of NUCLEAR SCIENCE and TECHNOLOGY   Vol. 45 ( 10 ) page: 1-9   2008.10

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    Laboratory-scale experiments for removing Mo and MoO3 from molten borosilicate glass were performed
    using liquid Cu as an extractant. Removal of Mo from the simulated HLW glass containing oxides
    of Nd, Fe, Zr, Mo, Sn, Ni, Sr, Cd, Ru, and Se was also performed, and the fractions of these elements
    transferred into Cu were examined. Mixtures of Cu and a ternary SiO2-B2O3-Na2O glass containing metallic
    Mo or MoO3 were heated in an alumina crucible at 1,673K in an Ar environment. The amounts of
    Mo and MoO3 added to 10 g of the ternary glass were fixed at 0.1 and 0.15 g, respectively. As for the glass
    containing metallic Mo, more than 90% of Mo was extracted into liquid Cu. Spherical Cu metal buttons
    containing Mo formed on the bottom of the crucible when Cu was added at more than 10 times that of Mo
    on a mass basis. Removal of Mo from the glass containing MoO3 was also achieved by the addition of Si
    as a reducing agent for the reduction from MoO3 to Mo. The fraction of Mo extracted into liquid Cu depended
    on the molar ratio of Si to Cu added to the glass. The fraction increased up to 84% with an increase
    in the molar ratio of Si/Cu. However, the excess addition of Si may enhance the chemical interaction between
    the metal phase and the glass phase, and some of the metal phase containing Mo remained in the
    glass phase without forming a metal button. The optimum molar ratio of Si/Cu that produces the highest
    removal fraction was found to be approximately 0.5. Almost the same removal fraction of 88% was obtained
    from the simulated HLW glass under the condition of Si/Cu = 0.5. Nearly 100% of Ru was extracted
    into Cu with Mo, while Sr, Zr, and Nd were hardly extracted and remained in the glass.

  22. Recovery of Metals from Simulated High-Level Radioactive Waste Glassthrough Phase Separation Reviewed

    Kazuyoshi URUGA, Kunio DOKA, Kayo SAWADA, Youichi ENOKIDA and Ichiro YAMAMOTO

    Journal of NUCLEAR SCIENCE and TECHNOLOGY   Vol. 45 ( 9 ) page: 1-10   2008.9

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    The recovery of metals from simulated high-level radioactive waste (HLW) in a glass form using the
    phase separation of borosilicate glass was studied in order to satisfy possible future demands such as the
    adoption of some new treatments for the waste in the glass or use of the vitrified elements as resources.
    The simulated HLW glass was separated into SiO2-rich and B2O3-rich phases at 973 and 873K when the
    ternary mass ratio of SiO2:B2O3:Na2O was adjusted to 68:27:5 by the addition of SiO2 and B2O3 to the
    simulated HLW glass. Annealing at the lower temperature of 878K promoted the distribution of the
    elements in the B2O3-rich phase. Approximately 90% of the Ni, Zn, Fe, Nd, Te, Zr, and Mo were distributed
    in the B2O3-rich phase, and these elements, except Zr, were almost completely leached into
    1 mol dm3 nitric acid at 363 K. The leaching of Zr was also achieved using 1.5 mol dm3 sulfuric acid
    after the nitric acid leaching. The leached fractions of the glass-network components, such as B and
    Al, were lower than the other elements at approximately 70–80% due to the existence of the SiO2-rich
    phase. An increase in the concentration of CaO in the glass in the range of 2–5 wt% inhibited the distribution
    of elements into the B2O3-rich phase. The increase in the concentration of CaO also changed
    the structure of the B2O3-rich phase from the continuous unit shape to the discontinuous spherical shape.
    Consequently, the leaching fraction of every element dramatically decreased. The structure of the B2O3-
    rich phase returned to continuous when the concentration of CaO was more than 10 wt%. From this glass,
    the leaching of 69% Zr was possible using only nitric acid without any sulfuric acid.

  23. RETRIEVABILITY OF METALS IN THE BOROSILICATE GLASS FOR NUCLEAR WASTE Reviewed

    Youichi Enokida, Kayo Sawada, Kazuyoshi Uruga

    The Proceedings of The High Level Radioactive Waste Management Conference   Vol. CD-ROM   2008.9

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    The recovery of metals from simulated high-level
    radioactive waste (HLW) in a borosilicate glass form was
    studied using the phase separation of borosilicate glass in
    order to satisfy possible future demands such as the
    adoption of some new treatments for the waste in the
    glass or use of the vitrified elements as mineral resources.

  24. BACK-EXTRACTION OF METAL SPECIES FROM SUPERCRITICAL CARBON DIOXIDE MODIFIED WITH TRI-n-BUTYL PHOSPHATE Reviewed

    Y. Enokida, K. Sawada, Y. Katakami

    The Proceedings of The International Solvent Extraction Conference   Vol. 2   page: 1627-1632   2008.9

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    a method is proposed for directly extracting heavy metals from solid matrices using supercritical carbon dioxide modified with tri-n-butyl phosphate (TBP) in the form of its nitric acid complex and has been shown to be effective for the recovery of uranium and plutonium from the solid powder of nuclear fuel for fast breeder reactors. The back extraction of uranium from supercritical carbon dioxide modified with TBP into an aqueous phase at ambient pressure or onto porous silica beads at high pressure is reported.

  25. Preparation of hydrophobic platinum catalysts using a water-in-CO2 microemulsion Reviewed

    Ryosuke Shimizu,Akihito Nibe, Kayo Sawada, Youichi Enokida, Ichiro Yamamoto

    JOURNAL OF SUPERCRITICAL FLUIDS   Vol. 44 ( 01 ) page: 109-114   2008.2

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    The hydrophobic platinum catalyst for the chemical exchange reaction between water and hydrogen was prepared by the two-step reduction of 1,5-cyclooctadiene dimethyl platinum (11): A reduction using the reducing agent of sodium tetraborohydrate solution in a water-in-CO2 microemulsion and the auto-catalytic reduction using hydrogen gas. The platinum particles were locally dispersed on the nano-textured hydrophobic layer formed on the gauze. Their average size was about 50 nm in diameter using a scanning electron microscope and energy dispersive X-ray spectroscopy. The hydrophobicity of the gauze did not decrease even after the deposition of the platinum nano-particles based on a measurement of the amount of water absorbed on the gauze. The hydrophobic platinum catalyst developed in this study was found to be effective for the isotopic exchange reaction of hydrogen atoms between hydrogen and deuterium even in the presence of water. The hydrogen and deuterium atoms were dissociated and exchanged with each other on the surface of the platinum particles and HD was generated. The HD/D-2 ratio increased from 0.012 to 0.050.

  26. Fundamental studies on extraction of actinides from spent fuels using liquefied gases - Conversion of copper into nitrate with NO2 and extraction of Nd(III) nitrate by CO2 with TBP Reviewed

    Kayo Sawada,Daisuke Hirabayashi,Youichi Enokida

    PROGRESS IN NUCLEAR ENERGY   Vol. 50 ( 2-6 ) page: 483-486   2008

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    The nitrate conversion with liquefied NO2 and the nitrate extraction with SC-CO2 were demonstrated for copper powder and neodymium nitrate instead of actinide compounds. Copper contacted with NO2 in an autoclave at 353 K changed to water-soluble compounds. By XRD analysis of the product in the atmospheric condition, the formation of copper nitrate hydrate (Cu(NO3)(2) center dot 2.5H(2)O) was confirmed. As for the extraction, neodymium nitrate loaded in an autoclave was successfully extracted with the fluid of TBP and SC-CO2 at 15 MPa, 313 K.

  27. Vitrification of high-level radioactive waste considering the behavior of platinum group metals Reviewed

    Kazuyoshi Uruga, Kayo Sawada, Youichi Enokida, Ichiro Yamamoto,

    PROGRESS IN NUCLEAR ENERGY   Vol. 50 ( 2-6 ) page: 514-517   2008

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    To demonstrate a method using liquid metal for the removal of PGMs during the vitrification process of high-level radioactive waste, removal of Pd was performed using Cu from molten glass containing fission products such as Nd, Sr, Zr, Mo, Te and Ni. Almost all the Pd, 93%, was extracted into liquid Cu and removed as a separable Cu-Pd metal button from the glass. Tellurium and Ni were also extracted 42 and 5.6%, respectively. Nearly 100% of the other elements, especially the heat generating elements such as Sr and Cs, for which Na was used as a substitute of Cs remained in the glass.

  28. Proceedings of the International Conference on Advanced Nuclear Fuel Cycle and Systems Reviewed

    Y.Enokida, K. Sawada , T. Shimada, I. Yamamoto

    Proceedings of the International Conference on Advanced Nuclear Fuel Cycle and Systems   Vol. CD-ROM   2007.9

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  29. Electrochemical studies on uranium in the presence of organic acids Reviewed

    Yoshinori Suzuki, Takuya Nankawa, Takuo Ozaki, Toshihiko Ohnuki, Arokiasarny J. Francis, Youichi Enokida, Ichiro Yamamoto

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 44 ( 09 ) page: 1227-1232   2007.9

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    We examined electrochemical redox reactions of UO22+ in perchlorate and organic acid (oxalic, malonic, succinic, adipic, L-malic, and L-tartaric acids) solutions using cyclic voltammetry to reveal the effects of complex formation with organic acids on the redox behavior. In the perchlorate and organic acid solutions, a redox reaction of UO22+/UO2+ and an oxidation reaction of U(TV) produced by a disproportionation Of UO2+ were observed. The peak potentials of the UO22+ reduction showed a good linear relationship with the stability constants of 1:1 UO22+-organic complexes. In the presence of malonic acid, the redox potential for UO22+/UO2+ was constant at pH 1-2 and 5-6 while it decreased with an increase in pH from 2 to 5. Additionally, it was independent of inalonate concentration at 0.1-0.5 M while it decreased with an increase in the concentration from 0.005 to 0.1 M. Based on the experimental and the speciation calculation results, we determined the redox reactions Of UO22+-malonate complexes as a function of pH and malonate concentration. We also determined the redox reactions Of UO22+-oxalate complexes in the same way.

  30. Decontamination of Tritiated Water Using Superhydrophobic Pt-Catalyst Synthesized with Water-in-Supercritical CO2 Reviewed

    Y.Enokida, R.Shimizu, K. Sawada, I. Yasmamoto

    Proceedings of American Nuclear Society Topical Meeting on Decomissioning, Decontamination and Reutilizatio   Vol. CD-ROM   2007.9

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  31. Extraction of Uranium from Spent Fuels Using Liquefied Gases Reviewed

    K. Sawada, D. Hirabayashi, Y. Enokida

    Proceedings of the International Conference on Advanced Nuclear Fuel Cycle and Systems   Vol. CD-ROM   2007.9

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  32. Removal of platinum group metals contained in molten glass using copper Reviewed

    Kazuyoshi Uruga, Kayo Sawada, Yuji Arita, Youichi Enokida, Ichiro Yamamoto

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 44 ( 7 )   2007.7

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    Removal of platinum group metals (PGMs) such as Pd, Ru, and RuO2 from molten glass by using various amounts of liquid Cu was done as a basic study on a new vitrification process for a high-level radioactive waste. We prepared two types of borosilicate glasses containing PGMs and Cu, respectively. These glasses were mixed together and heated at 1,473 K for 4 h in Ar atmosphere. More than 95% of Pd were removed as a spherical metal button composed of Pd-Cu alloy when Cu was added in an amount 0.5 times the weight of Pd. Nearly 95% of Ru was also removed as a spherical button with 2.5-5 times as much Cu addition as Ru in weight. Ruthenium oxide was reduced to metallic Ru by a reaction with Cu in the molten glass. The removal fraction was increased by increasing the amount of Cu and reached 63% when Cu addition was 7.5 times as much as RuO2 in weight. By addition of Si as a reducing agent, nearly 90% of Pd and Ru were removed with Cu and Si metal composites even under O-2 :Ar = 20:80 (v/v) condition.

  33. 超臨界直接抽出法による再処理プラントの概念と特徴 Reviewed

    島田隆,小雲信哉,石原信夫,澤田佳代,榎田洋一,山本一良

    日本原子力学会和文論文誌   Vol. 6 ( 2 ) page: 214-224   2007.6

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  34. Selective extraction of uranium from a mixture of metal or matal oxides by tri-n-butylphosphate complex with HNO3 and H2O in supercritical CO2 Reviewed

    T. Shimada, S. Ogumo, K. Sawada, Y. Enokida, I. Yamamoto

    Analytical Sciences   Vol. 22   page: 1387-1391   2006.11

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  35. Extractability of metals in municipal solid wastes fly ash using supercritical CO2 containinf Cyanex307 Reviewed

    K. Sawada, Y. Enokida, I. Yamamoto

    Analytical Sciences   Vol. 22   page: 1465-1467   2006.11

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  36. Decontamination of radioactive contaminants from iron pipes using reactive microemulsion of organic acid in supercritical carbon dioxide Reviewed

    R. Shimizu, K. Sawada, Y. Enokida, I. Yamamoto

    Journal of Nuclear Science and Technology   Vol. 43 ( 6 ) page: 694-698   2006.6

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  37. Densities of supercritical fluids containing CO2 and tri-n-butylphosphate Reviewed

    K. Sawada, O. Tomioka, T. Shimada, Y. Mori, Y. Enokida, I. Yamamoto

    Journal of Nuclear Science and Technology   Vol. 43 ( 1 ) page: 98-102   2006.1

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  38. Reduction behavior of uranium in the presencce of citric acid Reviewed

    Y. Suzuki, T. Nankawa, T. Yoshida, T. Ozaki, T. Ohnuki, A. J. Francis, S. Tsushima, Y. Enokida, I. Yamamoto

    Radiochim. Acta   Vol. 94   page: 579-583   2006

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  39. Dissolution of organic acids in supercritical CO2 using a CO2-philic Lewis base carrier Reviewed

    J. S. Wang, J. Herman, Y. Enokida, C. M. Wai

    JOURNAL OF SUPERCRITICAL FLUIDS   Vol. 36 ( 2 ) page: 98-105   2005.12

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  40. Sorption of Eu(III) on Pseudomonas fluorescens in the presence of citric acid, Journal of Nuclear and Radiochemical Science Reviewed

    Y. Suzuki, T. Nankawa, T. Yoshida, T. Ozaki, T. Onuki, A. J. Francis, S. Tsushima, Y. Enokida, I. Yamamoto

    Journal of Nuclear and Radiochemical Science   Vol. 6 ( 1 ) page: 91-93   2005.11

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  41. Generation of nitrous acid by ultrasound irradiation in the organic solution consisting of tri-n-butylphosphate, nitric acid and water Reviewed

    R. Shimizu, K. Sawada, Y. Enokida, I. Yamamoto

    Journal of Nuclear Science and Technology   Vol. 42 ( 11 ) page: 979-983   2005.11

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  42. Biotransformation of Eu(III)-citrate complex by pseudomonas fluorescens Reviewed

    Y. Suzuki, T. Yoshida, T. Ozaki, T. Ohnuki, A. J. Francis, S. Tsushima, Y. Enokida, I. Yamamoto

    Journal of radioanalytical and nuclear chemistry   Vol. 266   page: 199-204   2005.9

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  43. Hydrogen isotope separation by combined electrolysis catalytic exchange under reduced pressure Reviewed

    T. Sugiyama, Y. Asakura, T. Uda, Y. Abe, T. Shiozaki, Y. Enokida, I. Yamamoto

    FUSION SCIENCE AND TECHNOLOGY   Vol. 48 ( 1 ) page: 132-135   2005.8

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  44. Stoichiometric relation for extraction of uranium from UO2 powder using TBP complex with HNO3 and H2O in supercritical CO2 Reviewed

    K. Sawada, K. Uruga, T. Koyama, T. Shimada, Y. Mori, Y. Enokida, I. Yamamoto

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 42 ( 3 ) page: 301-304   2005.3

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  45. Supercritical fluid extraction of rare earth elements from luminescent material in waste fluorescent lamps Reviewed

    R. Shimizu, K. Sawada, Y. Enokida, I. Yamamoto

    JOURNAL OF SUPERCRITICAL FLUIDS   Vol. 33 ( 3 ) page: 237-243   2005.3

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  46. Dissolution of organic acids in supercritical CO2 using a CO2-philic Lewis base carrier Reviewed

    J. S. Wang, J. Herman, Y. Enokida, C. M. Wai

    The Journal of Supercritical Fluids   Vol. 36 ( 2 ) page: 98-105   2005.2

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    Solubility of hydrophilic organic acids in supercritical CO2 (SC-CO2) can be significantly increased utilizing a CO2-soluble Lewis base tri-n-butylphosphate (TBP) as a carrier. Solubilities of the acids carried by TBP are enhanced roughly by one order of magnitude for both citric acid and benzoic acid and a factor of 6 for lactic acid compared with those for each individual acid alone in SC-CO2.

  47. Biodegradation of Eu(III)-citrate complexes by Pseudomonas fluoresecens Reviewed

    Y. Suzuki, T. Nankawa, T. Ozaki, T. Ohnuki, A. J. Francis, S. Tsushima, Y. Enokida, I. Yamamoto

    Journal of Radioanalytical and Nuclear Chemistry   Vol. 266 ( 2 ) page: 199-204   2005.2

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  48. Decontamination of uranium oxides from solid wastes by supercritical CO2 fluid leaching method using HNO3-TBP complex as a reactant Reviewed

    JOURNAL OF SUPERCRITICAL FLUIDS   Vol. 31 ( 2 ) page: 141-147   2004.10

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  49. Preliminary experiments on hydrogen isotope separation by water-hydrogen chemical exchange under reduced pressure Reviewed

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 41 ( 6 ) page: 696-701   2004.6

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  50. *Characterization of a tri-n-butyl phosphate-nitric acid complex: a CO2-soluble extractant for dissolution of uranium dioxide Reviewed

    Industrial and Engineering Chemistry Research   Vol. 42 ( 21 ) page: 5037-5041   2003.10

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  51. H2-HT separation using "cryogenic-wall" thermal diffusion column with heated-tube Reviewed

    Fusion Science and Technology   Vol. 44 ( 6 ) page: 415-419   2003.9

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  52. H-2-HT separation using "cryogenic-wall" thermal diffusion column with heated-tube Reviewed

    Kobayashi N, Hirano R, Enokida Y, Yamamoto I

    FUSION SCIENCE AND TECHNOLOGY   Vol. 44 ( 2 ) page: 415-419   2003.9

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  53. Use of supercritical carbon dioxide for chromatographic separation of lithium isotopes Invited Reviewed

    the Eighth Workshop on Separation Phenomena in Liquids and Gases, October 12-16, 2003, Oak Ridge, Tennessee, U.S.A.   Vol. CD-ROM   2003

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  54. Application of supercritical fluid extraction to nuclear fuel reprocessing in Japan Invited

    Proceedings of the 1st International Symposium on Supercritical Fluid Technology for Energy and Environment Applications   Vol. 1   page: 35-41   2002

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  55. *Ultrasound-enhanced dissolution of UO2 in supercritical CO2 containing a CO2-philic complexant of tri-n-butylphosphate and nitric acid Reviewed

    Industrial and Engineering Chemistry Research   Vol. 41   page: 2282-2286   2002

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  56. Application of supercritical fluid extraction to nuclear fuel reprocessing in Japan, The First International Symposium on Supercritical Fluid Technology for Energy and Environment Application, Suwon, Korea, November 3-6, 2002. Invited

      Vol. 1   2002

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  57. Application of supercritical fluid extraction to nuclear fuel reprocessing in Japan, The First International Symposium on Supercritical Fluid Technology for Energy and Environment Application, Suwon, Korea, November 3-6, 2002. Invited

      Vol. 1   2002

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  58. Uranium Extraction from Nuclear Wastes with a High Pressure Mixture of CO2 and TBP Complex with Nitric Acid Reviewed

    Proceedings of 9th Biennial International Conference on Nuclear and Hazardous Waste Management, SPECTRUM 2002   Vol. CD-ROM   2002

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  59. Selective Recovery of Neodymium from Oxides by Direct Extraction Method with Supercritical CO2 Containing TBP-HNO3 Complex Reviewed

    Separation Science and Technology   Vol. 37   page: 1153-1162   2002

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  60. Nitrogen isotope separation with displacement chromatography using cryptand polymer Reviewed

    Journal of Nuclear Science and Technology   Vol. 39   page: 442-446   2002

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  61. Isotope Separation of H2-HD Gas Mixture with "Cryogenic-Wall" Thermal Diffusion Column with a Heated Tube Reviewed

    Journal of Nuclear Science and Technology   Vol. 39   page: 431-434   2002

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  62. Vapor-liquid equilibrium of UO2(NO3)22TBP and supercritical carbon dioxide mixture Reviewed

    Journal of Nuclear Science and Technology   Vol. Supplement ( 3 ) page: 270-273   2002

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  63. Dissolution behavior of uranium oxides with supercritical CO2 using HNO3-TBP complex as a reactant Reviewed

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 38 ( 12 )   2001

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  64. Isotopic approximations to thermal diffusion factor and ordinary diffusion coefficients in a mixture of more than 4 components Reviewed

    Journal of Nuclear Science and Technology   Vol. 38   page: 682-688   2001

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  65. New method for the removal of uranium from solid wastes with supercritical CO2 medium containing HNO3-TBP complex Reviewed

    Journal of Nuclear Science and Technology   Vol. 38   page: 461-462   2001

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  66. Lanthanides Extraction from Their Oxides with Supercritical Carbon Dioxide Containing Tri-n-butylphosphate Nitric Acid Complex Reviewed

    Proceedings of International Conference on Nuclear and Hazardous Waste Management, CR-DOM, Treatment Technology   Vol. CD-ROM   page: I-2   2001

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  67. 超高周速遠心機内部の2次元流れ解析

    日本原子力学会2000年秋の大会要旨集     page: I24   2000

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  68. Numerical Analyses of Isotopic Concentration Profiles in Displacement Chromatography for Lithium Isotope Separation

    Journal of Nuclear Science and Technology   Vol. 37   page: 267-272   2000

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  69. Separative Analyses of Packed Water Distil-lation Column with Channeling Stage ModelJournal

    of Nuclear Science and Technology   Vol. 37   page: 273-280   2000

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  70. Lanthanides Extraction from Their Oxides with Supercritical Carbon Dioxide Containing Tri-n-butylphosphate Nitric Acid Complex

    Proceedings of International Conference on Nuclear and Hazardous Waste Management     page: 18   2000

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  71. Selective Supercritical Fluid Extraction of Metals from their Oxides

    Proceedings of the 4th Japan-Korea Seminar on Advanced Reactors     page: 145-152   2000

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  72. 超臨界流体を用いた再処理システム(直接抽出法)の開発(3)ウラン抽出濃度に対する温度,圧力の影響

    日本原子力学会2000年春の年会要旨集     page: J16   2000

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  73. 超臨界二酸化炭素抽出法を用いたランタニド元素の分離

    日本原子力学会2000年秋の大会要旨集     page: I50   2000

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  74. 超臨界流体を用いた再処理システム(直接抽出法)の開発(5),可視化試験

    日本原子力学会2000年秋の大会要旨集     page: I49   2000

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  75. 超臨界流体を用いた再処理システム(直接抽出法)の開発(4),TBP硝酸錯体によるウラン溶解試験

    日本原子力学会2000年秋の大会要旨集     page: I48   2000

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  76. 窒素三成分系の熱拡散塔による分離性能評価

    日本原子力学会2000年秋の大会要旨集     page: I23   2000

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  77. 水蒸留法による重水からのトリチウム分離の基礎研究(Ⅱ)

    日本原子力学会2000年秋の大会要旨集     page: I22   2000

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  78. 水蒸留法による重水からのトリチウム分離の基礎研究(Ⅰ)

    日本原子力学会2000年秋の大会要旨集     page: I21   2000

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  79. 超臨界二酸化炭素中でのTBP錯体によるガドリニウムの除染

    日本原子力学会2000年秋の大会要旨集     page: I53   2000

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  80. Cleaning of Materials Contaminated with Metal Oxides through Supercritical Fluid Ex-traction with CO2 Containing TBP Reviewed

    O. Tomioka, Y. Enokida, I. Yamamoto, T. Takahashi

    Progress in Nuclear Energy   Vol. 37   page: 417-422   2000

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  81. Estimation of hot wire temperature of thermal diffusion column by the pressure change after turning on electricity Reviewed

    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   Vol. 37 ( 9 ) page: 807-813   2000

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  82. 超臨界流体を用いた再処理システム(直接抽出法)の開発(1)直接抽出法のシステムの概要と特徴

    日本原子力学会2000年春の年会要旨集     page: J14   2000

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  83. 超臨界二酸化炭素抽出法における混合された金属酸化物からのランタニドの選択的回収

    日本原子力学会2000年秋の大会要旨集     page: I51   2000

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  84. 超臨界二酸化炭素へのTBP硝酸錯体の溶解度

    日本原子力学会2000年秋の大会要旨集     page: I52   2000

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  85. Thermal Diffusion Factor for Diatomic Gas Mixture in Multicomponent System

    Journal of Nuclear Science and Technology   Vol. 37   page: 397-404   2000

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  86. Effect of Cold Wall Temperature of Thermal Diffusion Column on 14N15N-14N2 Isotope Separation

    Journal of Nuclear Science and Technology   Vol. 37   page: 710-715   2000

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  87. ジアミド化合物を含む超臨界二酸化炭素を用いた硝酸水溶液中からのランタニド抽出

    日本原子力学会中部支部第31回研究発表会要旨集     page: F1   1999

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  88. Numerical Analysis of Concentration Profiles of 4-Component Isotope Mixture within Gas Cetrifuges

    Proceedings of the 6th International Sympo-sium on Separation Phenomena in Liquid and Gases     page: 100-108   1999

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  89. Numerical Analysis of Non-Steady Flow and Separation Behavior in the Thermal Diffusion Column

    Proceedings of the 6th International Symposium on Separation Phenomena in Liquid and Gases     page: 437-446   1999

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  90. Numerical Analysis of Internal Flow and Separative Performance of a Packing for H2O-HTO Separation by Water Distillation

    Proceedings of the 6th International Sympo-sium on Separation Phenomena in Liquid and Gases     page: 427-436   1999

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  91. 充填物内部の構造が水蒸留塔の分離性能に及ぼす影響

    日本原子力学会1999年秋の大会要旨集     page: J24   1999

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  92. 通り抜け段モデルによる水蒸留充填塔の分離性能解析

    日本原子力学会1999年秋の大会要旨集     page: J23   1999

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  93. 熱拡散塔内高圧運転時の流れの振動が分離性能に及ぼす影響

    日本原子力学会中部支部第31回研究発表会要旨集     page: G1   1999

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  94. 超臨界二酸化炭素抽出法における混合酸化物からの選択的元素分離

    日本原子力学会1999年秋の大会要旨集     page: K54   1999

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  95. クリプタンド樹脂を用いた置換クロマトグラフィLi同位体分離における水の混入が分離挙動に与える影響

    日本原子力学会中部支部第31回研究発表会要旨集     page: F2   1999

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  96. 充填水蒸留塔を用いた水素同位体分離において充填物表面の濡れの違いが分離性能に及ぼす影響の評価

    日本原子力学会中部支部第31回研究発表会要旨集     page: A1   1999

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  97. モンテカルロシミュレーションを用いたTBPの超臨二酸化炭素への溶解度計算

    日本原子力学会中部支部第31回研究発表会要旨集     page: F3   1999

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  98. A Solution of a Material Balance Equation of Channeling Stage Model for a Simple Case of a Water Distillation Column

    Journal of Nuclear Science and Technology   Vol. 36   page: 959-961   1999

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  99. . Experimental and Numerical Analyses on Separative Performance by Displacement Chromatographic Separation of Li Isotope

    Proceedings of the 6th International Sympo-sium on Separation Phenomena in Liquid and Gases     page: 400-410   1999

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  100. モンテカルロシミュレーションを用いたTBPの超臨界二酸化炭素への溶解度計算手法の開発

    日本原子力学会1999年秋の大会要旨集     page: K53   1999

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  101. FBR Fuel Cycle with Reducing Amount of Reprocessed Uranium and Plutonium

    Proceedings of the 4th Nuclear Energy Symposium     page: 3-1-1~10   1999

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  102. Effect of Operational Pressure on Periodic Oscillation of Secondary Circulation near the Bottom of the Thermal Diffusion Column

    Journal of Nuclear Science and Technology   Vol. 36   page: 297-303   1999

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  103. 熱拡散法による窒素同位体分離実験

    日本原子力学会1999年春の年会1999年3月     page: 665   1999

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  104. Numerical Analysis of Dynamic Behavior at Start-up of the Thermal Diffusion Column for Hydrogen Isotope Separation

    Journal of Nuclear Science and Technology   Vol. 36   page: 198-203   1999

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  105. 液相内流動を考慮した充填水蒸留塔分離性能解析手法の開発

    日本原子力学会1999年春の年会1999年3月     page: 664   1999

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  106. Effects of Partition Wall within Packings on Separative Performances of Water Distillation for H2O-HTO Isotope Separation

    Journal of Nuclear Science and Technology   Vol. 36   page: 691-697   1999

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  107. Solvent Extraction of Lanthanides from their Oxides with TBP in Supercritical CO2

    JAERI-Conf 99-004     page: 486-490   1998

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  108. 新しい核燃料リサイクルシステムの展望 Invited

    日本原子力学会「先端技術と原子力」講演要旨集     page: 7-16   1998

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  109. Inverse Power Series Fittings of Temperature Dependence of Thermal Diffusion Factors Between Two Components of Hydrogen Isotope Molecules

    Journal of Nuclear Science and Technology   Vol. 35   page: 234-239   1998

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  110. バイパス流による液相内混合を考慮した充填水蒸留塔分離性能解析手法の開発

    日本原子力学会中部支部第30回研究発表会1998年12月     page: 6   1998

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  111. Feasibility Study of Nitride Fuel Core and Recycle System toward Self-Consistent Nuclear Energy System

    Progress in Nuclear Energy   Vol. 32   page: 673-680   1998

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  112. Simultaneous Solution of Concentration Profiles in Vapor-liquid Phases of Wetted-wall Distillation Column for H2O-HTO Isotope Separation

    Journal of Nuclear Science and Technology   Vol. 35   page: 60-65   1998

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  113. 置換クロマトグラフィLi同位体分離におけるLi同位体濃縮挙動解析

    日本原子力学会1998年(第36回)春の年会要旨集   Vol. III   page: 565   1998

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  114. 均質化理論を用いた充填水蒸留塔内の水素同位体濃縮挙動解析

    日本原子力学会1998年(第36回)春の年会要旨集   Vol. III   page: 564   1998

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  115. Solvent Extraction of Lanthanides from Their Oxides with TBP in Supercritical CO2

    Journal of Nuclear Science and Technology   Vol. 35   page: 515-516   1998

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  116. 超臨界二酸化炭素を媒体としたランタニド酸化物の直接抽出法の開発

    日本原子力学会1998年(第36回)春の年会要旨集   Vol. III   page: 544   1998

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  117. クリプタンド樹脂及びイオン交換樹脂を用いた置換クロマトグラフィLi同位体分離における溶液の線速度が分離性能に与える影響

    日本原子力学会1998年(第36回)春の年会要旨集   Vol. III   page: 566   1998

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  118. Effect of Inner Radius of Wetted-wall Column on Separative Performance of H2O-HTO Water Distillation

    Journal of Nuclear Science and Technology   Vol. 35   page: 723-727   1998

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  119. Effect of Flow Rate on Height Equivalent to a Theoretical Plate for Lithium Isotope Separation with Displacement Chromatography

    Journal of Nuclear Science and Technology   Vol. 35   page: 692-696   1998

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  120. Effect of Gravity and Intermolecular Potential on 3He-4He Separative Performance of"Cryogenic-Wall"Thermal Diffusion Column

    Fusion Engineering and Design   Vol. 39/40   page: 1015-1020   1998

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  121. Channeling Stage Model for Separative Analysis of Packed Water Distillation Column

    Fusion Engineering and Design   Vol. 39/40   page: 1027-1032   1998

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  122. Effect of Development Speed on Separative Performance of Displacement Chromatography Using Porous Ion Exchange Resin for Li Isotope Separation

    Fusion Engineering and Design   Vol. 39/40   page: 1009-1013   1998

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  123. 超臨界二酸化炭素を媒体としたランタニド酸化物の直接抽出法における抽出率に対する硝酸濃度の影響

    日本原子力学会1998年秋の大会,1998年10月     page: 692   1998

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  124. Development of Fuel Recycle Based on Dry Pyrochemical Processing Technology

    Proceedings of the 5th International Nuclear Conference on RSecycling, Conditioning and Disposal, RECOD 98     page: 125-133   1998

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  125. 多成分系同位体分離用遠心機の濃度分布解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 51   1997

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  126. Distribution Coefficient Correlations for Nitric Acid, U(VI) and Pu(IV) in Two-Phase System with Aqueous Nitric Acid and 30% Tri-n-Butyl Phosphate Solutions

    Journal of Nuclear Science and Technology   Vol. 34   page: 700-707   1997

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  127. 濡れ壁水蒸留塔の分離性能解析(I)

    日本原子力学会1997年春の年会要旨集     page: 594   1997

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  128. Feasibility Study of Nitride Fuel Core and Recycle System toward Self-consistent Nuclear Energy System Reviewed

    Proceedings of Global'97   Vol. 2   page: 1038-1043   1997

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  129. 同位体分離用熱拡散塔における最適圧力の塔長依存性

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 35   1997

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  130. 均質化理論を用いた充填水蒸留塔内部濃度分布解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 32   1997

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  131. 深冷壁熱拡散塔による15N濃縮カスケードの解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 1   1997

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  132. 濡れ壁水蒸留塔の分離性能解析(II)

    日本原子力学会1997年春の年会要旨集     page: 595   1997

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  133. 置換クロマトグラフィLi同位体分離時の同位体濃縮挙動解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 47   1997

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  134. 水素同位体分子6成分系の熱拡散塔分離性能解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 42   1997

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  135. 熱拡散塔内部での水素同位体濃縮挙動の解析

    日本原子力学会中部支部第29回研究発表会講演予稿集     page: 37   1997

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  136. Efficient Use of Dry Pyrochemical Processing for FBR Fuel Recycling

    Proceedings of Global'97   Vol. 1   page: 313-318   1997

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  137. Feasibility Study of Nitride Fuel Core and Recycle System toward Self-consistent Nuclear Energy System

    Proceedings of the 2nd International Symposium on Global Environment and Nuclear Energy Systems     page: 87   1996

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  138. FBR核燃料リサイクルシステム概念の検討(その3)-乾式熱処理技術の開発検討-

    日本原子力学会1996年春の年会要旨集     page: 602   1996

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  139. Process Design Improvement through Simulation Analysis of Dissolution and Separation Processes for Nuclear Fuel Reprocessing

    Proceedings of the 3rd JSME/ASME Joint International Conference on Nuclear Engineering   Vol. 4   page: 1865-1870   1995

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  140. HDEHP-TBP混合溶媒を用いたAmと希土類元素の分配試験

    日本原子力学会1995年秋の大会要旨集     page: 716   1995

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  141. FBR核燃料リサイクルシステム概念の検討(その1)-システム概念-

    日本原子力学会1995年秋の大会要旨集     page: 524   1995

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  142. 照射済燃料溶解液のよう素追出し方法に関する研究(その2)

    日本原子力学会1994年秋の大会要旨集     page: 40   1994

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  143. 単純化PUREXプロセス(MSPUREXプロセス)に関する検討

    日本原子力学会1994年春の年会要旨集     page: 49   1994

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  144. Extraction Behavior of Nitric Acid and Neptunium by CMPO+TBP Mixture

    Proceedings of International Solvent Extraction Conference'93   Vol. 1   1994

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  145. Application of Electrically Driven Liquid-Liquid Dispersion to Solvent Extraction Using Tri-n-Buthyl Phosphate Reviewed

    Tsuyoshi Usami, Youichi Enokida, Atsuyuki Suzuki

    Journal of Nuclear Science and Technology   Vol. 30 ( 10 ) page: 1017-1023   1993.10

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    DOI: 10.3327/jnst.30.1017

  146. Neptunium Separation from Nitric Acid Solutions with CMPO

    Proceedings of RECOD'94   Vol. III   page: 1813-1820   1993

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  147. 光酸化還元反応の核燃料再処理への応用 Reviewed

    ケミカルエンジニアリング   Vol. 38 ( 8 ) page: 37-42   1993

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  148. Photochemical reduction of U(VI)at Low Temperature in Aqueous Nitric Acid Solution and Its Application Feasibility to Solvent Extraction Process

    Proceedings of International Solvent Extraction Conference'93   Vol. III   page: 1554-1551   1993

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  149. Solvent Extraction of Neptunium by n-Octyl(phenyl)-N, N-Diisobuthylcarbamoylmethlphosphine Oxide from Nitric Acid Solution Containing Hydrogen Peroxide

    Solvent Extraction and Ion Exchange   Vol. 11   page: 377-387   1993

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  150. Application of Electrically Driven Liquid-Liquid Dispersion to Solvent Extraction Using Tri-n-Butyl Phosphate

    Journal of Nuclear Science and Technology   Vol. 30   page: 1017-1023   1993

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  151. Third Phase Formation in Nitric Acid Extraction by n-Octyl(phenyl)-N, N-Diisobuthylcarbamoylmethlphosphine Oxide

    Solvent Extraction and Exchange   Vol. 12   page: 459-473   1993

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  152. Temperature Effect on the Extraction of Np(V) by n-Octyl(phenyl)-N, N-Diisobuthylcarbamoylmethlphosphine Oxide

    Solvent Extraction and Ion Exchange   Vol. 11   page: 569-583   1993

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  153. Determination of Uranium(VI) over Wide Concentration Ranges in Aqueous Nitric Acid and 30% Tri-n-Butyl Phosphate by Laser-Induced Thermal Lensing Spectroscopy

    Radiochimica Acta   Vol. 57   page: 101-104   1992

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  154. Oxidation of Pentavalent Neptunium by Nitrous Acid in CMPO-TBP-n-Dodecane Organic Solution

    Journal of Nuclear Science and Technology   Vol. 29   page: 671-676   1992

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  155. 熱レンズ振動を利用したリン酸トリブチル中でのアクチニドイオンの濃度測定

    日本原子力学会1992年春の年会要旨集     page: 79   1992

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  156. 晶析によるウラン精製への光化学の応用

    日本原子力学会1992年春の年会要旨集     page: 60   1992

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  157. Application of Laser-Induced Thermal Lens Oscillation to Concentration Measurement in Organic Solutions

    Journal of Nuclear Science and Technology   Vol. 29   page: 255-262   1992

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  158. Estimation of Uranium(VI)Concentrations by Temperature Profiles in Solvent Extraction Processes with 30% Tri-n-Butyl Phosphate Diluted by n-Dodecane

    Journal of Nuclear Science and Technology   Vol. 29   page: 461-471   1992

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  159. Effect of TBP on Solvent Extraction of Np(V)with n-Octyl(phenyl)-N, N-Diisobuthylcarbamoylmethlphosphine Oxide

    Journal of Nuclear Science and Technology   Vol. 29   page: 263-268   1992

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  160. 再処理工程における電解による化学種の濃度測定

    日本原子力学会1992年秋の大会要旨集     page: 417   1992

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  161. 低温におけるウラン光還元の核燃料再処理への応用

    化学工学会第25回秋季大会講演要旨集   Vol. 1   page: 0.147   1992

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  162. Solvent Extraction of Np(V)with CMPO from Nitric Acid Solution Containing U(VI)

    Journal of Nuclear Science and Technology   Vol. 29   page: 1100-1107   1992

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  163. CMPOによる超ウラン元素溶媒抽出工程での濃度分布

    日本原子力学会1992年秋の大会要旨集     page: 457   1992

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  164. 熱レンズ振動を利用したアクチニドの濃度測定

    日本原子力学会1992年秋の大会要旨集     page: 418   1992

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  165. 30%リン酸トリブチルによる硝酸,U(VI),Pu(IV)抽出分配比モデルの改良とその影響評価

    日本原子力学会1992年秋の大会要旨集     page: 410   1992

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  166. CMPOによるNp(V),Np(VI)の抽出における温度依存性と抽出速度

    日本原子力学会1992年春の年会要旨集     page: 147   1992

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  167. CMPOによるNp(V),Np(VI)の抽出挙動

    日本原子力学会1992年春の年会要旨集     page: 150   1992

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  168. 共除染工程における溶媒流量変化に伴う過渡事象の解析

    日本原子力学会1992年春の年会要旨集     page: 56   1992

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  169. Basic Photochemical Studies of Plutonium and Neptunium

    Proceedings of the Third International Conference on Nuclear Fuel Reprocessing and Waste Management   Vol. II   page: 809-813   1991

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  170. PUREXプロセスにおける計算機コードの開発

    日本原子力学会1991年秋の大会要旨集     page: 662   1991

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  171. 交流電場抽出機によるTBP-硝酸系での液液抽出(II)

    日本原子力学会1991年秋の大会要旨集     page: 665   1991

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  172. Laser-Induced Thermal Lens Spectroscopy for Actinide Determination in Aqueous and Organic Solutions

    Proceedings of the Third International Conference on Nuclear Fuel Reprocessing and Waste Management   Vol. II   page: 875-880   1991

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  173. 30%TBP(70%n-dodecane)によるウラン溶媒抽出工程での温度分布による濃度分布の推算

    日本原子力学会1991年秋の大会要旨集     page: 663   1991

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  174. CMPO-TBP-n-dodecane系での硝酸抽出における第3相形成,

    日本原子力学会1991年秋の大会要旨集     page: 602   1991

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  175. CMPOによるNp(V)抽出における温度依存性と共同効果に関する研究

    日本原子力学会1991年秋の大会要旨集     page: 598   1991

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  176. アクチニド元素の光化学分離についての基礎研究(II)

    日本原子力学会1991年秋の大会要旨集     page: 676   1991

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  177. ネプツニウムおよびプルトニウムの光化学分離に関する基礎試験

    PNCTN841090-050   Vol. PNCTN841090-050   page: 1-55   1990

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  178. アクチニド元素の光化学分離(1)

    日本原子力学会1990年秋の大会要旨集     page: 641   1990

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  179. レーザーによる放射性溶液の処理 Invited Reviewed

    レーザー学会誌   Vol. 18   page: 267-278   1990

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  180. Basic Photochemical Studies of Plutonium and Neptunium

    Proceedings of the First OECD/NEA Information Exchange Meeting for Separation and Transmutation of Actinides and Fission Products     page: 21-22   1990

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  181. Neptunium Valence Adjustment through Photochemically Induced Redox Reactions at Low Concentrations

    Journal of Nuclear Science and Technology   Vol. 26   page: 770-776   1989

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  182. 塔型抽出装置の流動不安定性解析

    東京大学工学部総合試験所年報   Vol. 48   page: 131-134   1989

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  183. Reduction Stripping of Low-Concentration Np(Vl)Loaded on 30% Tri-n-Butyl Phosphate through Laser-Induced Reactions

    Nuclear Technology   Vol. 88   page: 47-54   1989

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  184. アクチノイドおよび白金族の熱レンズ法による濃度分析の検討

    東京大学工学部総合試験所年報   Vol. 48   page: 125-129   1989

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  185. レーザー分離プロセスの最適化

    東京大学原子力研究総合センター   Vol. UTRCN-K-20   page: 227-230   1989

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  186. Axial Turbulent Diffusion in Fluid between Rotating Concentric Cylinders

    Annual Report of the Engineering Research Institute   Vol. 48   page: 119-124   1989

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  187. Axial Turbulent Diffusion in Fluid between Rotating Coaxial Cylinders

    AlChE Journal   Vol. 35   page: 1211-1214   1989

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  188. レーザーによるボロン同位体分離

    東京大学工学部総合試験所年報   Vol. 48   page: 149-153   1989

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  189. レーザー光電離特性の解析

    東京大学工学部総合試験所年報   Vol. 48   page: 143-148   1989

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  190. 回転円筒型抽出装置の特性解析

    日本原子力学会1989年秋の大会要旨集   Vol. II   page: 137   1989

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  191. 熱レンズ法による低濃度アクチノイドの分析

    日本原子力学会1989年秋の大会要旨集   Vol. II   page: 107   1989

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  192. 塔型抽出装置における密度対流の解析(I)

    日本原子力学会昭和63年秋の大会要旨集   Vol. II   page: 218   1988

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  193. Laser Isotope Separation by Deep Burning Method

    Annual Report of the Engineering Research Institute   Vol. 47   page: 103-108   1988

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  194. 小型回転円筒型抽出装置の流動特性

    日本原子力学会昭和63年秋の大会要旨集   Vol. II   page: 220   1988

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  195. レーザー技術,再処理への応用

    日本原子力学会「原子燃料サイクル」研究専門委員会トピカルミーティング「原子燃料サイクルにおける新技術とその応用」講演要旨集     page: 14-15   1988

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    Authorship:Lead author   Language:Japanese  

  196. 核燃料再処理と廃棄物管理国際学会 Reviewed

    日本原子力学会誌   Vol. 30   page: 31-33   1988

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  197. レーザー分離プロセスの最適化

    東京大学原子力研究総合センター   Vol. UNRCN-K-19   page: 211-214   1988

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  198. 塔型抽出装置における密度対流の解析(II)

    日本原子力学会昭和63年秋の大会要旨集   Vol. II   page: 219   1988

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  199. 核燃料再処理におけるレーザーによるネプツニウムの分離

    東京大学工学部紀要B   Vol. 46   page: 95-110   1987

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  200. Laser Photochemical Neptunium Separation

    Proceedings of International Conference on Nuclear Fuel Reprocessing and Waste Management, RECOD'87   Vol. 1   page: 475-482   1987

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    Authorship:Lead author   Language:English   Publishing type:Research paper (scientific journal)  

  201. 円環型パルスカラムの液液分散特性

    東京大学工学部紀要A   Vol. 25   page: 42-43   1987

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  202. パルスカラム分離部内液滴累積槽厚みへの微粒子混入の影響

    日本原子力学会昭和62年秋の大会要旨集   Vol. II   page: 319   1987

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  203. 円環型パルスカラム内の液液分散特性

    日本原子力学会昭和62年年会要旨集   Vol. II   page: 171   1987

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  204. 核燃料再処理へのレーザー分離プロセスの応用

    東京大学工学部原子力工学科   Vol. NEUT Research Report   page: 1-59   1987

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  205. レーザー分離プロセスの研究

    東京大学原子力研究総合センター   Vol. UTRCN-K-18   page: 197-200   1987

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  206. レーザー光分離プロセスの解析 Reviewed

    原子力工業   Vol. 33 ( 1 ) page: 27-32   1987

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  207. Extraction-Chromatographic Measurement of Oxidation State of Neptunium-237 at Low Concentrations

    Journal of Nuclear Science and Technology   Vol. 24   page: 859-861   1987

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    Authorship:Lead author   Language:English   Publishing type:Research paper (scientific journal)  

  208. 核燃料再処理における光化学によるネプツニウムの原子価調整

    東京大学工学部紀要B   Vol. 45   page: 113-116   1986

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  209. Application of Laser Photochemistry to Neptunium Separation Processes

    Proceedings of World Congress III of Chemical Engineering   Vol. 1   page: 700-703   1986

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  210. エキシマ・レーザーを利用したネプツニウム水溶液の原子価調整

    日本原子力学会昭和61年年会要旨集   Vol. II   page: 254   1986

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  211. レーザー分離プロセスの研究

    東京大学原子力研究総合センター   Vol. UTRCN-K-16   page: 197-200   1986

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  212. 長寿命放射性廃棄物の処理に関する基礎研究

    東京大学原子力研究総合センター   Vol. UTRCN-K-15   page: 168-171   1985

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  213. 将来における原子炉安全性,研究と規制 Reviewed

    日本原子力学会誌   Vol. 27   page: 610-611   1985

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  214. 光化学による超ウラン元素の分離

    東京大学工学部原子力工学科   Vol. NEUT Research Report   page: 1-55   1985

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  215. 光化学による超ウラン元素の分離

    東京大学原子力研究総合センター   Vol. UTRCN-S-9   page: 43-44   1985

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  216. 米国における高レベル廃棄物管理の動向とその分析 Reviewed

    日本原子力学会誌   Vol. 27   page: 708-709   1985

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  217. 長寿命放射性廃棄物の処理に関する基礎研究

    東京大学原子力研究総合センター   Vol. UTRCN-K-14   page: 227-228   1984

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  218. 光化学を利用したネプツニウム水溶液の原子価調整

    日本原子力学会昭和59年秋の分科会要旨集   Vol. II   page: 203   1984

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  219. 光化学による超ウラン元素の分離

    東京大学原子力研究総合センターニュース   Vol. 12   page: 7-10   1984

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    Authorship:Lead author   Language:Japanese   Publishing type:Research paper (bulletin of university, research institution)  

  220. 光化学によるアクチノイド元素の分離 Invited Reviewed

    Radioisotopes   Vol. 33   page: 34   1983

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  221. Long-term Risk Assessment on High-Level Waste Management

    Proceedings of PACHEC'83   Vol. III   page: 344-349   1983

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  222. 放射性廃棄物処理への光化学の応用に関する基礎研究

    日本原子力学会昭和58年秋の分科会要旨集   Vol. II   page: 9   1983

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  223. 水プールから溶融する底板への熱伝達, Reviewed

    東京大学工学部紀要A   Vol. 19   page: 50-51   1981

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Books 10

  1. Annual Report for Nuclear Energy Systems Committee

    Youichi Enokida( Role: Joint author ,  Preface)

    Chubu Chapter, Atomic Energy Society of Japan  2021.3 

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    Total pages:89   Responsible for pages:3   Language:Japanese Book type:Report

  2. Annual Report for Nuclear Energy Systems Committee

    Youichi Enokida( Role: Joint author ,  Preface)

    Chubu Chapter, Atomic Energy Society of Japan  2020.3 

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    Total pages:81   Responsible for pages:3   Language:Japanese Book type:Report

  3. Annual Report on Nuclear Energy Systems Research Committee

    Youichi Enokida et al.( Role: Joint author ,  Preface)

    Chubu Chapter, The Atomic Energy Society of Japan  2019.3 

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    Total pages:100   Responsible for pages:1   Language:Japanese Book type:Report

    Concerning to th current nuclear energy systems, a comprehensive studies are performed and reported from standpoints of global energy policy, nuclear reactor type strategy, public acceptance of nuclear energy utilization.

  4. Extraction of uranium and lanthanides from their oxides with a high-pressure mixture of TBP-HNO3-H2O-CO2

    ( Role: Joint author)

    ACS Symposium Series  2003 

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    Language:English

  5. Extraction of uranium and lanthanides from their oxides with TBP-HNO3-H2O-CO2

    Abstracts of Papers of the American Chemical Society, 223: 218-IEC, Part 1, 2002  2002 

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    Language:English

  6. 超臨界流体を用いた核燃料再処理技術(直接抽出法)の開発

    ( Role: Joint author)

    日本原子力学会「先端技術と原子力」講演要旨集  2000 

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    Language:Japanese

  7. Application of Laser-Induced Thermal Lens Oscillation to Concentration Control in Solvent Extraction Processes In Instabilities in Multiphase Flows

    Plenum Publishing Corporation  1993 

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    Language:English

  8. レーザー技術,再処理への応用,原子燃料サイクルにおける新技術とその応用

    ( Role: Sole author)

    日本原子力学会  1989 

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    Language:Japanese

  9. レーザーの液相プロセスへの応用,レーザー技術と将来に向けたその応用

    ( Role: Sole author)

    日本原子力学会  1988 

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  10. (W. Marshall, "Nuclear Power Technology, Vol. 2, Chapter 15 ; The Management of Radioactive Waste from Civil Nuclear Power Generation, Claredon Press, 1983の分担共訳)

    1987 

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    Language:Japanese

▼display all

Presentations 139

  1. 同位体分析を目的とした超音速プラズマ中のストロンチウム蛍光スペクトル測定

    桑原彬,早川禎一郎,澤田佳代,榎田洋一

    日本原子力学会2021年春の年会  2021.3.18  日本原子力学会

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    Event date: 2021.3

    Language:Japanese  

    Venue:早稲田大学   Country:Japan  

  2. Extraction of Palladium with Di-n-hexyl Sulfide by Micro Bubble Generator

    Chenyu Zhou, Kayo Sawada, Akira Kuwahara, Youichi Enokida

    2020.12.18  Chubu local branch of the Atomic Energy Society of Japan

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    Event date: 2020.12 - 2021.12

    Language:English  

    Venue:Nagoya University   Country:Japan  

  3. アークジェットによる運動方向を制御したアルゴンプラズマを対象としたレーザー誘起蛍光システムの開発

    早川禎一郎,桑原彬,澤田佳代,榎田洋一

    第52回日本原子力学会中部支部研究発表会  2020.12.18  日本原子力学会中部支部

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    Event date: 2020.12

    Language:Japanese  

    Venue:名古屋大学   Country:Japan  

  4. Influence of specific area on solubility of molybdenum into the host glass

    Takumi Shimakura, Kayo Sawada, Akira Kuwahara, Youichi Enokida

    52nd Research Meeting of Chubu Local Branch of the Atomic Energy Society of Japan  Chubu local branch of the Atomic Energy Society of Japan

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    Event date: 2020.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:Nagoya University   Country:Japan  

  5. セシウム吸着ゼオライトのガラス固化処理における結晶形成に及ぼすB2O3添加の影響

    氣田 雅大, 澤田 佳代, 桑原 彬, 榎田 洋一

    第52回日本原子力学会中部支部研究発表会  日本原子力学会中部支部

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    Event date: 2020.12

    Language:Japanese  

    Venue:名古屋大学   Country:Japan  

  6. Ca含有ホウケイ酸ガラスによるNa2MoO4の溶融挙動

    澤田佳代,嶋倉匠海,榎田洋一,塚田毅志

    日本原子力学会2019年秋の大会  2020.9.18  日本原子力学会

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    Event date: 2020.9

    Language:Japanese  

    Venue:リモート開催   Country:Japan  

  7. 水‐水素化学交換に用いる疎水性白金触媒の調製とその耐久性

    森田洋平,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会2014年春の年会 

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    Event date: 2015.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:茨城大学   Country:Japan  

    トリチウム分離を目的とする水‐水素化学交換に用いる疎水性白金触媒の調製とその耐久性について実験研究を行い,基盤的知見を明らかにした.

  8. Leaching rate of the borosilicate glass containing molybdenum oxide International conference

    K. Fujii, Y. Ota, K. Sawada, T. Sugiyama, Y. Enokida

    Waste Management Symposia 2015 

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    Event date: 2015.3

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  9. ホウケイ酸ガラスへの酸化モリブデンの溶解度に及ぼす組成の影響

    藤井宏治, 澤田佳代, 杉山貴彦, 榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    ホウケイ酸ガラスへの酸化モリブデンの溶解度に及ぼす組成の影響を実験研究とモデルに基づき考察した.

  10. ホウケイ酸ガラスの構造解析と耐浸出性能評価

    太田祐希,藤井宏治,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    多核固体核磁気共鳴法を活用して,ホウケイ酸ガラスの構造解析を行うとともに実験研究により耐浸出性能評価も行い,ガラス構造との関係を明確化した.

  11. 運転温度および圧力が異なる2つの水-水素化学交換塔を組み合わせた装置の分離性能評価

    高田暁人,森田洋平,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    運転温度および圧力が異なる2つの水-水素化学交換塔を組み合わせた水素同位体分離装置の実験による原理実証とモデル解析による分離性能評価を行い,よい一致を得た.

  12. 重金属を含むフッ化物の水溶液化に関する研究

    北埜元樹,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    ループ型フッ化物溶融塩原子炉の成立性を検討する基礎データを取得するために,重金属を含むフッ化物の水溶液化に関する分析手法の開発を行った.

  13. 中和反応で生成する水酸化ウラニル沈殿中の共存ナトリウム量のpH依存性

    平山和樹,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    中和反応で生成する水酸化ウラニル沈殿中の共存ナトリウム量のpH依存性をウランを用いた実験研究で明らかにした.

  14. 多孔質シリカビーズを用いたシリカ含有率の高いガラス固化体の作製

    [7] 佐野泰,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    多孔質シリカビーズを用いたシリカ含有率の高いガラス固化体の作製方法について実験研究を行い,十分な可能性を原理実証した.

  15. 高圧二酸化炭素で増強した水性二相系による金属イオンの抽出

    大坊祥太,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    Re, Mo, Ruを対象とした,高圧二酸化炭素で増強した水性二相系による金属イオンの抽出について,実験研究を行い得た成果を報告している.

  16. 担体の疎水性の強化による白金触媒の水素同位体交換性能の向上

    森田洋平,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    担体の疎水性の強化による白金触媒の水素同位体交換性能の向上についてトリチウムを用いて実験研究で検討した.

  17. 高レベルガラス固化体製造における仮焼層からのルテニウム化合物の揮発とその抑制

    上田泰之,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    高レベルガラス固化体製造における仮焼層からのルテニウム化合物の揮発量とそのショ棟による抑制効果を実験研究で検討した.

  18. 超撥水性柔軟多孔体を担体に用いた水-水素化学交換用白金触媒の調整 International conference

    [3] 中村航平,森田洋平,杉山貴彦,澤田佳代,榎田洋一

    日本原子力学会中部支部第46回研究発表会 

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    Event date: 2014.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    超撥水性柔軟多孔体を担体に用いて新規な水-水素化学交換用白金触媒の調整を行うことに成功した.

  19. ホウケイ酸ガラスの浸出性に及ぼす酸化モリブデンの影響

    藤井宏治, 澤田佳代, 杉山貴彦, 榎田洋一

    日本原子力学会2014年秋の大会 

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    Event date: 2014.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    ホウケイ酸ガラスの浸出性に及ぼす酸化モリブデンの影響を実験研究によって検討した.

  20. Carbonation enhanced extraction of Metal ions in Aqueous two-phase system using polyetylene for Nuclear Waste Processing International conference

    Y. Enokida, S. Daibo, T. Sugiyama, K. Sawada

    ACS Northwest Regeonal Meeting 2014 

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    Event date: 2014.6

    Language:English   Presentation type:Oral presentation (general)  

    Country:United States  

    Liquid-liquid extraction of metal ions in an aqueous two-phase system using aqueous
    solution of polyethylene glycol and sodium or potassium carbonate is experimentally studied to extend
    applicable metal species from TcO4- to RuO4
    2- and MoO4
    2- for nuclear waste treatment. Salting effect of
    using aqueous carbonate ions is experimentally investigated and use of high pressure carbon dioxide is
    discussed. As a consequence, the aqueous two-phase system using polyethylene glycol and sodium
    carbonate solution can be applied to extract not only TcO4
    - but also other anions of metal oxides for
    energy applications and high pressure carbon dioxide could be of use for salting.

  21. 22) Supercritical carbon dioxide enhanced extraction of metal ions in an aqueous two-phase system using polyethylene glycol International conference

    Y. Enokida, K. Sawada, S. Daibo

    14th European Meeting on Supercritical Fluids 

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    Event date: 2014.5

    Language:English   Presentation type:Oral presentation (general)  

    Country:France  

    Liquid-liquid extraction of metal ions in an aqueous two-phase system using aqueous solution of polyethylene glycol and sodium carbonate is experimentally studied to extend applicable metal species from TcO4- to RuO42- and MoO42- in nuclear energy application, and to MnO4- and CoO2- in recycling of raw materials for lithium ion batteries. Additionally, salting effect of using high pressure carbon dioxide is investigated. As a consequence, the aqueous two-phase system using polyethylene glycol and sodium carbonate solution can be applied to extract not only TcO4- but also other anions of metal oxides for energy applications and high pressure carbon dioxide is of use for salting.

  22. セシウム汚染土壌の塩化揮発法による除染に関する研究

    垣内章吾, 澤田佳代, 榎田洋一

    第45回日本原子力学会中部支部研究発表会 

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    Event date: 2013.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

    原子炉事故で放出され,土壌に吸着されたセシウムを塩化水素で除染する方法の有効性を粘土鉱物と多孔質シリカビーズを用いて粘土鉱物の寸法スケールと細孔拡散内拡散係数の評価値から検討し,代表寸法が10nm以上のスケールの粘土鉱物からの除染について有効性があることを確認した.

  23. Immobilization of zeolite adsorbing cesium by vitrification with borosilicate glass

    Y.Ota, N.Sako, T.Shimada, K.Sawada, Y.Enokida

    International Symposium on Ecotopia Science 

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    Event date: 2013.12

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

    Immobilization of zeolite adsorbing cesium through vitrification with borosilicate glass has been studied, and the vitrification has successfully been demonstrated using glass beads prepared for the adsorbent. dissipation of cesium during the vitrification was not observed and leaching rate of cesium from the vitrified specimens was low enough to meet the temporal regulation criterion.

  24. Tritium decontamination from heavy-oxygen water used positron emission tomography

    Takahiko Sugiyama, Akito Takada, Youichi Enokida, Ichiro Yamamoto

    The 11th symposium on The Society of Isotope Science  

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  25. Numerical analyses of mass transfer in core-shell adsorbent packed column for chromatographic separation of lithium isotope

    Takahiko Sugiyama, Kei Sugiura, Youichi Enokida, Ichiro Yamamoto

    The 11th symposium on The Society of Isotope Science  

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    Event date: 2013.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  26. セシウムを吸着したゼオライトのガラス固化処理のためのフリット組成の検討 International conference

    太田祐希,島田隆寛,佐光直樹,澤田佳代,杉山貴彦,平林大介,榎田洋一

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

  27. イオン性液体を溶媒として用いる置換クロマトグラフィー法によるネオジムの分離

    小笠原亨一,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

  28. 汚染土壌の粒径区分と放射性セシウム濃度の評価

    平林大介,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

  29. セシウムが吸着したゼオライトを対象としたセメント固化体の炭酸化処理

    神谷研人,澤田佳代,榎田洋一

    日本原子力学会中部支部第44回研究発表会 

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    Event date: 2012.12

    Language:English   Presentation type:Oral presentation (general)  

    Venue:名古屋大学   Country:Japan  

  30. 高レベル放射性廃液ガラス固化プロセスにおける酸化ルテニウムの析出

    日本原子力学会2010年秋の大会 

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    Event date: 2010.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    ガラス溶融炉内での高レベル放射性廃液のガラス固化を想定して,仮焼層を形成する硝酸ナトリウムとルテニウム化合物の反応について基礎試験を実施した結果、ルテニウム酸ナトリウムの生成をX線回折で確認した。また、これがホウケイ酸ガラスと接触する界面付近で酸化ルテニウムの針状結晶を生成することを顕微鏡観察等により確認した。

  31. Ultrasound-induced decomposition of dodecane using supercritical carbon dioxide in water microemulsion International conference

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Oral presentation (invited, special)  

    Country:Japan  

    Ultrasound-induced decomposition was experimentally demonstrated as a means for radioactive organic waste treatment in a system of supercritical fluid carbon dioxide (SF-CO2) in water (SFC/W) microemulsion. Ultrasound induced decomposition of organic wastes is promising when applied for the organic wastes containing radioactive contaminants because amount of the secondary radioactive waste generated in the treatment can be minimized. However, solubilities of organic compounds in water are usual

  32. Decomposition of NO2 and VOCs using uranium oxide

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  33. Synthesis of superhydrophobic platinum catalyst on stainless steel gauze in supercritical carbon dioxide International conference

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

    A superhydrophobic platinum-catalyst for hydrogen-atom exchange reaction between a diatom hydrogen molecule and a water molecule was synthesized using a series of procedures in supercritical CO2.

  34. Treatment and vitrification of spent catalyst for organic synthesis containing uranium and antimony International conference

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

    Decontamination of U and Sb from the spent uranium catalyst for organic synthesis for acrylonitrile and vitrification have been successfully demonstrated in a laboratory scale.

  35. Lanthanide extraction using chelating agents in aqueous phase

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  36. Immersion of fly ash in oxalic acid to recycle calcium as acid gas absorbent International conference

    The R'09 Twin World Congress 

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    Event date: 2009.9

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  37. Preparation of superhydrophobic surface on Gauze of stainless steel in supercritical carbon dioxide International conference

    American Chemical Society 64th Northwest Regional Meeting 

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    Event date: 2009.6

    Language:English   Presentation type:Oral presentation (general)  

    A method of preparation a superhydrophobic surface on inorganic materials, glass or metal of stainless steel in supercritical carbon dioxide has been developed. Sol-gel reactions of tetraethyl orthosilicate and/or tetraethyl orthotitanate in a microemulsion of water in supercritical carbon dioxide were employed to form roughness in submicron onto the inorganic materials being followed by coating of a hydrophobic organic reagent, 1H,1H,2H,2H-perfluorooctyl triethoxysilane dissolved in supercrit

  38. Synthesis of superhydrophobic platinum catalyst based on a supercritical CO2 platform International conference

    9th International Symposium on Supercritical Fluids 

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    Event date: 2009.5

    Language:English   Presentation type:Oral presentation (general)  

    A super-hydrophobic platinum-catalyst for hydrogen-atom exchange reaction between a diatom hydrogen molecule and a water molecules was synthesized using a series of procedures in supercritical CO2. Firstly superhydrophobic surface layer was prepared onto the surface of stainless steel gauze by a sol-gel reaction utilizing water-in CO2 microemulsion containing silicon and titanium alcoxides followed by deposition of platimun nano―particles through capillary condensation in tiny spaces in the s

  39. Actinide separation using solubility difference of the TBP complexes with their nitrates in supercritical carbon dioxide International conference

    9th International symposium on Supercritical Fluids 

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    Event date: 2009.5

    Language:English   Presentation type:Poster presentation  

  40. Synthesis of superhydrophobic platinum catalyst based on a supercritical CO2 platform International conference

    9th International Symposium on SuperCritical Fluids 2009 

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    Event date: 2009.5

    Language:English   Presentation type:Oral presentation (general)  

    A super-hydrophobic platinum-catalyst for hydrogen-atom exchange reaction between a diatom hydrogen molecule and a water molecules was synthesized using a series of procedures in supercritical CO2. Firstly superhydrophobic surface layer was prepared onto the surface of stainless steel gauze by a sol-gel reaction utilizing water-in CO2 microemulsion containing silicon and titanium alcoxides followed by deposition of platimun nano―particles through capillary condensation in tiny spaces in the s

  41. Formation of Ruthenim Dioxide DuringVitrification of HLW, and It's Effect onLeachability of the Glass International conference

    Waste Management symposia 

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    Event date: 2009.3

    Language:English   Presentation type:Poster presentation  

  42. 二酸化窒素の酸化ウランを用いた分解

    猪飼智治, 澤田佳代, 榎田洋一

    日本原子力学会中部支部第40回研究発表会 

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    Event date: 2008.12

    Language:Japanese   Presentation type:Poster presentation  

    Country:Japan  

  43. ゾルゲル法を用いた模擬高レベル放射性廃液のガラス固化

    安藤康哲, 澤田佳代, 榎田洋一

    日本原子力学会中部支部第40回研究発表会 

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    Event date: 2008.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  44. ランタニド抽出における水相へのキレート剤の添加の効果

    竹内百恵, 澤田佳代, 榎田洋一, K. Nash

    日本原子力学会中部支部第40回研究発表会 

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    Event date: 2008.12

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  45. BACK-EXTRACTION OF METAL SPECIES FROM SUPERCRITICALCARBON DIOXIDE MODIFIED WITH TRI-n-BUTYL PHOSPHATE International conference

    INTERNATIONAL SOLVENT EXTRACTION CONFERENCE 

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    Event date: 2008.9

    Language:English   Presentation type:Oral presentation (general)  

    The authors have proposed an method of extracting heavy metals directly from solid matrices
    using supercritical carbon dioxide modifies with tri-n-butyl phosphate (TBP) complexed initially
    with nitric acid, and demonstrated the extraction of uranium and plutonium from solid powder of
    nuclear fuel for fast breeder nuclear reactors. In the present paper, the authors report on back
    extraction of uranium from the supercritical carbon dioxide modified with TBP into aqueous
    phase at the ambient p

  46. RETRIEVABILITY OFMETALS IN THE BOROSILICATE GLASS FOR NUCLEAR WASTE International conference

    International High Level Radioactive Waste Management Conference 

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    Event date: 2008.9

    Language:English   Presentation type:Oral presentation (general)  

    The recovery of metals from simulated high-level
    radioactive waste (HLW) in a borosilicate glass form was
    studied using the phase separation of borosilicate glass in
    order to satisfy possible future demands such as the
    adoption of some new treatments for the waste in the
    glass or use of the vitrified elements as mineral resources.

  47. 超臨界二酸化炭素を用いて作製した水-水素同位体交換反応用白金触媒

    林田和之,澤田佳代,杉山貴彦,榎田洋一

    日本原子力学会2008年秋の大会 

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    Event date: 2008.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    ステンレス鋼製の金網上に蒸着した有機シリコン膜の100 nm程度の大きさの凸凹中に超臨界二酸化炭素中で生じる毛細管凝縮現象を利用して、白金ナノ粒子を担持させる新規製法で水ー水素同位体交換反応用の触媒を作製し、その機能の発現を確認した。

  48. 置換クロマトグラフィー法を用いたケイ素同位体分離(2)

    宮田章弘,杉山貴彦,澤田佳代,榎田洋一,山本一良

    日本原子力学会 2008年秋の大会 

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    Event date: 2008.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

    置換クロマトグラフィー法を用いたケイ素同位体分離について、イオン対の種類について実験研究を行い、その実施例を示すとともに、同位体分離への効果を議論した。

  49. 超臨界二酸化炭素を用いて作製した水-水素同位体交換反応用白金触媒

    林田和之, 澤田佳代, 榎田洋一, 山本一良

    日本原子力学会2008年秋の大会 

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    Event date: 2008.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  50. 置換クロマトグラフィー法によるケイ素同位体分離(2)

    宮田章弘, 杉山貴彦, 澤田佳代, 榎田洋一, 山本一良

    日本原子力学会2008年秋の大会 

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    Event date: 2008.9

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  51. 原子力人材教育における技術コミュニケーション教育の展開

    榎田洋一・澤田佳代・青柳雅

    原子力人材育成シンポジウム「稔りある原子力人材育成を目指して」 

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    Event date: 2008.6

    Language:Japanese   Presentation type:Oral presentation (invited, special)  

    Country:Japan  

    名古屋大学では、原子力分野における人材育成に資するため、「原子力人材教育における技術コミュニケーションの展開」と題して平成19年度原子力人材育成プログラム事業に応募して採択されたため、これを計画通りに実施した。この事業の概要について、簡単に紹介した。

  52. 超臨界流体を用いた全アクチニド一括分離システムの開発(4)FP の分配係数

    澤田佳代, 榎田洋一, 小山智造, 青木和夫

    日本原子力学会2008年春の年会 

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    Event date: 2008.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  53. 置換クロマトグラフィー法を用いたケイ素同位体分離

    宮田章弘, 杉山貴彦, 澤田佳代, 榎田洋一, 山本一良

    日本原子力学会2008年春の年会 

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    Event date: 2008.3

    Language:Japanese   Presentation type:Oral presentation (general)  

    Country:Japan  

  54. Extraction of Heavy Metals into Supercritical Carbon Dioxide and TheirBack Extraction for Nuclear Fuel Reprocessing International conference

    Korea-Japan Workshop on Nuclear Pyroprocessing 

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    Event date: 2008.1

    Language:English   Presentation type:Oral presentation (invited, special)  

    Country:Japan  

    We found mineral and organic acids can be introduced in supercritical carbon dioxide (SF-CO2) as complexes with tri-n-butylphosphate (TBP). Among them, TBP complex with nitric acid is useful to dissolve and extract metals from their oxides. Uranium and plutonium extraction from real nuclear fuel consisting of the mixed oxide where PuO2 forms a solid solution in UO2 was successfully demonstrated under a high pressure. This experiment was performed as a part of a collaboration work by Nagoya Un

  55. Nuclear Chemistry Related Researches in Nagoya University International conference

    Invited Talk in the Radiochemistry Group in the Department of Chemistry, Washington State University 

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    Event date: 2007.9

    Language:English   Presentation type:Oral presentation (invited, special)  

    Application Of Supercritical Fluid Extraction to Nuclear Fuel Reprocessing
    Chemical Activity of Aqueous Solutions of Highly Concentrated Nitrates for Solvent Extraction
    1.Separation of Tri-butyl Phosphate and Their Metal Complexes using Ionic Liquid Fixed on Silica Beads
    2. Removal of Platinum Group Metals and Molybdenum from Molten High Level Waste Glass using Liquid Copper
    3. Synthesis of Platinum Nanoparticles in Supercritical Carbon Dioxide for Hydrogen Isotope Separation

  56. Decontamination of Tritiated-Water Using Superhydrophobic Pt-Catalyst Synthesized with Water-in-Supercritical CO2 International conference

    ANS Topical Meeting on Decommissioning, Decontamination, and Reutilization 

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    Event date: 2007.9

    Language:English   Presentation type:Oral presentation (invited, special)  

    We demonstarated a new hydrophobic cataryst preparation using SC-CO2 effectively. We can conclude that the approach of creating Pt nanoparticles in SC-CO2 and depositing them in the superhydrophobic structure on the metal surface is useful for synthesizing hydrophilic catalysts for the hydrogen isotope separation.

  57. AN OPTION MAKING FOR NUCLEAR FUEL REPROCESSINGBY USING SUPERCRITICAL CARBON DIOXIDE International conference

    International Conference on Advanced Nuclear Fuel Cycles and Systems 

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    Event date: 2007.9

    Language:English   Presentation type:Oral presentation (general)  

    A fouryearresearch
    has been completed as a
    collaborative work by Nagoya University, Mitsubishi
    Heavy Industries Corporation and Japan Atomic
    Energy Agency (JAEA) in order to develop a super
    critical carbon dioxide (SFCO2)
    based technology,
    “SUPERDIREX
    process," for nuclear fuel
    reprocessing As a result obtained in Phase II of the
    Japan´s Feasibility Studies on Commercialized Fast
    Reactor Cycle Systems, this technology was
    evaluated as one of the alternatives for the advanced
    Pure

  58. Vitrification of high-level radioactive waste considering the behavior of platinum group metals

    The Second COE-INES International Symposium 

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    Event date: 2006.11

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  59. Extraction of actinides from spent fuels using liquefied gases

    The Seconde COE-INES International Symposium 

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    Event date: 2006.11

    Language:English   Presentation type:Poster presentation  

    Country:Japan  

  60. Solubility of neodymiun nitrate complexed with tri-n-butyl phosphate in supercritical carbon dioxide International conference

    17th International Congress of Chemical and Process Engineering 

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    Event date: 2006.8

    Language:English   Presentation type:Poster presentation  

  61. Processing of Nuclear Materials through Supercritical Carbon Dioxide, The 11th International Symposium on Supercritical Fluid Chromatography, Extraction, and Processing, Pittsburgh, Pennsylvania, USA, August 1-4, 2004. International conference

    The 11th International Symposium on Supercritical Fluid Chromatography, Extraction, and Processing, Pittsburgh, Pennsylvania, USA, August 1-4, 2004. 

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    Event date: 2004.8

    Language:English   Presentation type:Oral presentation (invited, special)  

  62. Direct extraction of uranium and plutonium from oxide fuel using TBP-HNO3 complex for Super-DIREX process International conference

    International Conference ATALANTE 2004 Advances for Future Nuclear Fuel Cycles 

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    Event date: 2004.6

    Language:English   Presentation type:Oral presentation (general)  

  63. Uranium Decontamination from Nuclear Wastes Using High Pressure Carbon Dioxide in Japan, , May 27, 2003. International conference

    Invited Seminar in Los Alamos National Laboratory 

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    Event date: 2003.5

    Language:English   Presentation type:Oral presentation (invited, special)  

  64. Application of supercritical fluid extraction to nuclear fuel reprocessing in Japan, The First International Symposium on Supercritical Fluid Technology for Energy and Environment Application, Suwon, Korea, November 3-6, 2002. Invited International conference

    Youichi Enokida

    Super Green 2002  2002.11.4  Kyung Hee University

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    Event date: 2002.11

    Language:English   Presentation type:Oral presentation (invited, special)  

    Venue:Suwon, Korea   Country:Korea, Republic of  

  65. Extraction of uranium and lanthanides from their oxides with TBP-HNO3-H2O-CO2 International conference

    Annual Meeting of American Chemical Society,Orland, Florida, USA 

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    Event date: 2002.4

    Language:English   Presentation type:Oral presentation (invited, special)  

  66. Extraction of uranium and lanthanides from their oxides with TBP-HNO3-H2O-CO2 International conference

    Abstracts of Papers of the American Chemical Society, 223: 218-IEC, Part 1, 2002 

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    Event date: 2002

    Language:English   Presentation type:Oral presentation (general)  

  67. Selective Supercritical Fluid Extraction of Metals from their Oxides, , October 20, 2000, Tokyo Institute of Technology, Tokyo, Japan.

    the 4th Japan-Korea Seminar on Advanced Reactors 

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    Event date: 2000.10

    Language:English   Presentation type:Oral presentation (invited, special)  

    Country:Japan  

  68. Treatment of Metal Oxides by Supercritical Fluid Extraction, International conference

    Symposium on Reduction of Environmental Impact with Nuclear Energy Use,Nagoya University, Nagoya, Japan. 

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    Event date: 2000.3

    Language:English   Presentation type:Oral presentation (general)  

    Country:Japan  

  69. 超臨界流体を用いた再処理システム(直接抽出法)の開発(1)直接抽出法のシステムの概要と特徴

    日本原子力学会2000年春の年会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  70. 超臨界二酸化炭素抽出法を用いたランタニド元素の分離

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  71. 超臨界流体を用いた再処理システム(直接抽出法)の開発(5),可視化試験

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  72. 超臨界流体を用いた再処理システム(直接抽出法)の開発(4),TBP硝酸錯体によるウラン溶解試験

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  73. 超高周速遠心機内部の2次元流れ解析

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  74. 窒素三成分系の熱拡散塔による分離性能評価

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  75. 水蒸留法による重水からのトリチウム分離の基礎研究(Ⅱ)

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  76. 水蒸留法による重水からのトリチウム分離の基礎研究(Ⅰ)

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  77. 超臨界流体を用いた再処理システム(直接抽出法)の開発(3)ウラン抽出濃度に対する温度,圧力の影響

    日本原子力学会2000年春の年会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  78. 超臨界二酸化炭素抽出法における混合された金属酸化物からのランタニドの選択的回収

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  79. 超臨界二酸化炭素中でのTBP錯体によるガドリニウムの除染

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  80. 超臨界二酸化炭素へのTBP硝酸錯体の溶解度

    日本原子力学会2000年秋の大会要旨集 

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    Event date: 2000

    Language:Japanese   Presentation type:Oral presentation (general)  

  81. FBR Fuel Cycle with Reducing Amount of Reprocessed Uranium and Plutonium, Taoyuan, Taiwan.

    the 4th Nuclear Energy Symposium 

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    Event date: 1999.3

    Language:English   Presentation type:Oral presentation (invited, special)  

  82. モンテカルロシミュレーションを用いたTBPの超臨界二酸化炭素への溶解度計算手法の開発

    日本原子力学会1999年秋の大会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  83. 充填水蒸留塔を用いた水素同位体分離において充填物表面の濡れの違いが分離性能に及ぼす影響の評価

    日本原子力学会中部支部第31回研究発表会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  84. 充填物内部の構造が水蒸留塔の分離性能に及ぼす影響

    日本原子力学会1999年秋の大会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  85. 通り抜け段モデルによる水蒸留充填塔の分離性能解析

    日本原子力学会1999年秋の大会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  86. 熱拡散塔内高圧運転時の流れの振動が分離性能に及ぼす影響

    日本原子力学会中部支部第31回研究発表会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  87. 液相内流動を考慮した充填水蒸留塔分離性能解析手法の開発

    日本原子力学会1999年春の年会1999年3月 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  88. 熱拡散法による窒素同位体分離実験

    日本原子力学会1999年春の年会1999年3月 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  89. モンテカルロシミュレーションを用いたTBPの超臨二酸化炭素への溶解度計算

    日本原子力学会中部支部第31回研究発表会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  90. ジアミド化合物を含む超臨界二酸化炭素を用いた硝酸水溶液中からのランタニド抽出

    日本原子力学会中部支部第31回研究発表会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  91. 超臨界二酸化炭素抽出法における混合酸化物からの選択的元素分離

    日本原子力学会1999年秋の大会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  92. クリプタンド樹脂を用いた置換クロマトグラフィLi同位体分離における水の混入が分離挙動に与える影響

    日本原子力学会中部支部第31回研究発表会要旨集 

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    Event date: 1999

    Language:Japanese   Presentation type:Oral presentation (general)  

  93. 超臨界二酸化炭素を媒体としたランタニド酸化物の直接抽出法における抽出率に対する硝酸濃度の影響

    日本原子力学会1998年秋の大会,1998年10月 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  94. バイパス流による液相内混合を考慮した充填水蒸留塔分離性能解析手法の開発

    日本原子力学会中部支部第30回研究発表会1998年12月 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  95. 均質化理論を用いた充填水蒸留塔内の水素同位体濃縮挙動解析

    日本原子力学会1998年(第36回)春の年会要旨集 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  96. 超臨界二酸化炭素を媒体としたランタニド酸化物の直接抽出法の開発

    日本原子力学会1998年(第36回)春の年会要旨集 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  97. クリプタンド樹脂及びイオン交換樹脂を用いた置換クロマトグラフィLi同位体分離における溶液の線速度が分離性能に与える影響

    日本原子力学会1998年(第36回)春の年会要旨集 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  98. 置換クロマトグラフィLi同位体分離におけるLi同位体濃縮挙動解析

    日本原子力学会1998年(第36回)春の年会要旨集 

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    Event date: 1998

    Language:Japanese   Presentation type:Oral presentation (general)  

  99. 濡れ壁水蒸留塔の分離性能解析(I)

    日本原子力学会1997年春の年会要旨集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  100. 多成分系同位体分離用遠心機の濃度分布解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  101. 置換クロマトグラフィLi同位体分離時の同位体濃縮挙動解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  102. 水素同位体分子6成分系の熱拡散塔分離性能解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  103. 熱拡散塔内部での水素同位体濃縮挙動の解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  104. 同位体分離用熱拡散塔における最適圧力の塔長依存性

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  105. 均質化理論を用いた充填水蒸留塔内部濃度分布解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  106. 深冷壁熱拡散塔による15N濃縮カスケードの解析

    日本原子力学会中部支部第29回研究発表会講演予稿集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  107. 濡れ壁水蒸留塔の分離性能解析(II)

    日本原子力学会1997年春の年会要旨集 

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    Event date: 1997

    Language:Japanese   Presentation type:Oral presentation (general)  

  108. FBR核燃料リサイクルシステム概念の検討(その3)-乾式熱処理技術の開発検討-

    日本原子力学会1996年春の年会要旨集 

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    Event date: 1996

    Language:Japanese   Presentation type:Oral presentation (general)  

  109. HDEHP-TBP混合溶媒を用いたAmと希土類元素の分配試験

    日本原子力学会1995年秋の大会要旨集 

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    Event date: 1995

    Language:Japanese   Presentation type:Oral presentation (general)  

  110. FBR核燃料リサイクルシステム概念の検討(その1)-システム概念-

    日本原子力学会1995年秋の大会要旨集 

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    Event date: 1995

    Language:Japanese   Presentation type:Oral presentation (general)  

  111. 単純化PUREXプロセス(MSPUREXプロセス)に関する検討

    日本原子力学会1994年春の年会要旨集 

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    Event date: 1994

    Language:Japanese   Presentation type:Oral presentation (general)  

  112. 照射済燃料溶解液のよう素追出し方法に関する研究(その2)

    日本原子力学会1994年秋の大会要旨集 

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    Event date: 1994

    Language:Japanese   Presentation type:Oral presentation (general)  

  113. 低温におけるウラン光還元の核燃料再処理への応用

    化学工学会第25回秋季大会講演要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  114. CMPOによるNp(V),Np(VI)の抽出における温度依存性と抽出速度

    日本原子力学会1992年春の年会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  115. CMPOによるNp(V),Np(VI)の抽出挙動

    日本原子力学会1992年春の年会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  116. 共除染工程における溶媒流量変化に伴う過渡事象の解析

    日本原子力学会1992年春の年会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  117. 晶析によるウラン精製への光化学の応用

    日本原子力学会1992年春の年会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  118. 熱レンズ振動を利用したリン酸トリブチル中でのアクチニドイオンの濃度測定

    日本原子力学会1992年春の年会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  119. CMPOによる超ウラン元素溶媒抽出工程での濃度分布

    日本原子力学会1992年秋の大会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  120. 再処理工程における電解による化学種の濃度測定

    日本原子力学会1992年秋の大会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  121. 30%リン酸トリブチルによる硝酸,U(VI),Pu(IV)抽出分配比モデルの改良とその影響評価

    日本原子力学会1992年秋の大会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  122. 熱レンズ振動を利用したアクチニドの濃度測定

    日本原子力学会1992年秋の大会要旨集 

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    Event date: 1992

    Language:Japanese   Presentation type:Oral presentation (general)  

  123. CMPOによるNp(V)抽出における温度依存性と共同効果に関する研究

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  124. アクチニド元素の光化学分離についての基礎研究(II)

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  125. 交流電場抽出機によるTBP-硝酸系での液液抽出(II)

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  126. PUREXプロセスにおける計算機コードの開発

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  127. 30%TBP(70%n-dodecane)によるウラン溶媒抽出工程での温度分布による濃度分布の推算

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  128. CMPO-TBP-n-dodecane系での硝酸抽出における第3相形成,

    日本原子力学会1991年秋の大会要旨集 

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    Event date: 1991

    Language:Japanese   Presentation type:Oral presentation (general)  

  129. アクチニド元素の光化学分離(1)

    日本原子力学会1990年秋の大会要旨集 

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    Event date: 1990

    Language:Japanese   Presentation type:Oral presentation (general)  

  130. 回転円筒型抽出装置の特性解析

    日本原子力学会1989年秋の大会要旨集 

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    Event date: 1989

    Language:Japanese   Presentation type:Oral presentation (general)  

  131. 熱レンズ法による低濃度アクチノイドの分析

    日本原子力学会1989年秋の大会要旨集 

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    Event date: 1989

    Language:Japanese   Presentation type:Oral presentation (general)  

  132. 小型回転円筒型抽出装置の流動特性

    日本原子力学会昭和63年秋の大会要旨集 

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    Event date: 1988

    Language:Japanese   Presentation type:Oral presentation (general)  

  133. 塔型抽出装置における密度対流の解析(II)

    日本原子力学会昭和63年秋の大会要旨集 

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    Event date: 1988

    Language:Japanese   Presentation type:Oral presentation (general)  

  134. 塔型抽出装置における密度対流の解析(I)

    日本原子力学会昭和63年秋の大会要旨集 

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    Event date: 1988

    Language:Japanese   Presentation type:Oral presentation (general)  

  135. パルスカラム分離部内液滴累積槽厚みへの微粒子混入の影響

    日本原子力学会昭和62年秋の大会要旨集 

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    Event date: 1987

    Language:Japanese   Presentation type:Oral presentation (general)  

  136. 円環型パルスカラム内の液液分散特性

    日本原子力学会昭和62年年会要旨集 

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    Event date: 1987

    Language:Japanese   Presentation type:Oral presentation (general)  

  137. エキシマ・レーザーを利用したネプツニウム水溶液の原子価調整

    日本原子力学会昭和61年年会要旨集 

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    Event date: 1986

    Language:Japanese   Presentation type:Oral presentation (general)  

  138. 光化学を利用したネプツニウム水溶液の原子価調整

    日本原子力学会昭和59年秋の分科会要旨集 

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    Event date: 1984

    Language:Japanese   Presentation type:Oral presentation (general)  

  139. 放射性廃棄物処理への光化学の応用に関する基礎研究

    日本原子力学会昭和58年秋の分科会要旨集 

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    Event date: 1983

    Language:Japanese   Presentation type:Oral presentation (general)  

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Works 8

  1. トリウム燃料を利用した原子炉開発の課題と展望

    2013.5

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    世界各国および我が国の研究開発状況を知り、今後の課題と展望を探る

  2. 国立大学法人 東京大学大学院工学系研究科原子力工学専攻外部評価書

    2009.4
    -
    2009.12

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    当該外部評価委員会委員長として報告書の執筆・とりまとめを行った。

  3. 微生物による白金族元素ナノ粒子触媒の作製に成功-微生物の不思議な力に迫る-

    2009.2
    -
    2009.3

  4. 放射性廃棄物処理現状や課題を講演

    2008.11

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    福井新聞平成20年11月28日記事

  5. *核燃料リサイクルを再考する

    2008.8

  6. 日本学術会議主催原子力総合シンポジウム2007パネリスト

    2007.5

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    日本学術会議主催、39学協会共催で日本学術会議講堂で実施され、「エネルギー教育―持続可能な成長基盤の確立へ向けた産・官・学一体の取り組みの始まり」についてパネル討論のパネリストとして招聘され、エコトピア科学研究所の研究方針に沿った提言を行った。すなわち、エコトピア社会で重要な原子力エネルギーの安全で安心な利用のためには、特に、技術コミニュケーションに素養のある人材育成が重要であ留ことを説明した。

  7. 科学技術・学術審議会 研究計画・評価分科会 原子力分野の研究開発に関する委員会「RI研究所等廃棄物作業部会」報告書

    2005.12
    -
    2007.7

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    原子力利用は、原子力発電やそれを支える核燃料サイクルだけではなく、研究開発、産業、医療等の幅広い範囲に及んでおり、これらの分野においては、放射性同位元素(RI)、放射線発生装置、核燃料物質等が活用されているが、これらに関連して排出される放射性廃棄物の処理処分について、政策展開と社会制度構築が十分ではなかったため、作業部会長として学識経験者からなる委員による審議を進め、報告書のとりまとめを行ったものであり、報告書は公開され、国民のパブリックコメントをすでに受けて文部科学政策に反映されつつある。報告書は内閣府原子力委員会での評価が行われ、高く評価されており、政策提言として内容も重要であることに加え、エコトピア科学研究所のビジョンのうちエネルギー利用と環境の調和に関する研究成果の実際的な社会還元成果のひとつと考えられる。また、この報告書に記述された社会状況の一部を解決するために、平成19年度の原子力人材育成に関わる公募事業における「エネルギー・環境制約社会での技術コミニュケーション」というテーマでの文理融合研究補助金の獲得にも努力し、研究所での文理融合研究の実践に大きく寄与した業績でもある。

  8. A bright idea for recycling dim bulbs A bright idea for recycling dim bulbs

    2005.1

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Research Project for Joint Research, Competitive Funding, etc. 7

  1. ガラス母材形態の廃棄物成分閉じ込め性能への影響

    2019.6 - 2020.3

    受託研究 

    澤田佳代

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    経済産業省が実施する『平成31年度放射性廃棄物の減容化へ向けたガラス固化技術の基盤研究事業』のうち,「ガラスマトリックス・原料供給形態の高度化」に関して,一般財団法人電力中央研究所からの再委託を受けて,ガラス母材形態の廃棄物成分閉じ込め性能への影響について研究する.

  2. Feasibilty study on vitrification process by lead borate glass for reductive waste in basic study for vitrification study for volume reduction of waste

    2018.6 - 2019.2

    Commissioned Research 

    Kayo Sawada

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    Feasibilty study wasperformed on vitrification process by lead borate glass for reductive waste in basic study for vitrification study for volume reduction of waste. Fundamental aspects and supportive data for the feasibilty had been obtained.

  3. エネルギー・環境制約下における技術コミニュケーション

    2007.7 - 2008.3

    原子力人材育成事業 

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    Grant type:Competitive

    放射性廃棄物処分場のように原子力研究開発や原子力産業の健全な発展において、必要不可欠であるものの、広く地域社会において、立地やそれに関わる合意形成が難しい施設が存在する。例えば、放射性廃棄物処分場の立地に関しては、放射線安全学や核燃料サイクル工学のような原子力特有の基礎分野における技術的に広範で正しい知識に加えて、「技術コミュニケーション」あるいはより細分化された専門分野として「リスクコミミュニケーション」と称される学術分野に関する教育を受けた人材を育成することが重要である。しかし、これまでの大学や大学院における原子力工学教育では、このような「技術コミュニケーション」教育については、必ずしも重要視されてきておらず、実際に「正しい科学技術知識を正しく伝える」こと自体を教授できる人材に欠けているのが実情である。また、最近の社会事情や今後ますます高まるであろう組織の法令遵守に対する社会的要請を鑑みるとき、科学技術に対する広く深い専門的知識と技術コミュニケーションに対する専門的知識および経験の両方を有する人材は、原子力産業界だけではなく、広く日本や世界において求められている人材像であり、大学における原子力教育によって、このような人材を輩出できることは、社会における原子力教育を受けた人材の需要を増大させ、原子力特有の技術分野への間接的な理解の増進にも寄与するものと考えられる。このためには、現在の大学における原子力特有の基礎分野である例えば核燃料サイクル工学の教授陣の「技術コミュニケーション」教育に関わる教育・指導能力を高める取り組みがまずは肝要であり、ここで提案する事業では、既に核燃料サイクル工学の分野で教育と研究を行っている大学教員を「技術コミュニケーション」に関する研究会に参加させ、「技術コミュニケーション」に関する学術的素養を習得させるとともに、学生指導に必要な教材、例えば、事例研究集の開発等を通じて、所属する大学における学生や社会人に対するコンカレント教育等への対応能力を養うものである。

  4. 高圧水中超臨界二酸化炭素マイクロエマルションでの超音波照射による有機物分解法

    2005.7 - 2008.3

  5. SuperDirex再処理法による使用済燃料からのU, Pu直接抽出法に関する技術開発

    2001 - 2005.3

    革新的実用原子力技術開発公募研究 

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    Grant type:Competitive

  6. Study on Dissolution and Extraction of Metal Oxides with Supercritical Fluid, PartII

    2000

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    Grant type:Competitive

  7. Study on Dissolution and Extraction of Metal Oxides with Supercritical Fluid, PartI

    1999

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    Grant type:Competitive

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KAKENHI (Grants-in-Aid for Scientific Research) 3

  1. 高圧水中超臨界二酸化炭素マイクロエマルションでの超音波照射による有機物分解法  

    2006

    科学研究費補助金  萌芽研究,課題番号:18656271

    榎田 洋一

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    Authorship:Principal investigator 

  2. ナノ構造を用いて創製する高機能触媒を利用する水素同位体分離手法の開発

    2005.7 - 2008.3

    科学研究費補助金  基盤研究(A),課題番号:16206096

    榎田 洋一

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    Authorship:Principal investigator 

  3. 超臨界二酸化炭素中で安定化されたナノ構造を利用する局在化した放射性物質の抽出

    2005.7 - 2008.3

    科学研究費補助金  萌芽研究,課題番号:15656239

    榎田 洋一

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    Authorship:Principal investigator 

Industrial property rights 13

  1. トリチウム除去装置及びトリチウム除去方法

    杉山貴彦,榎田洋一,山本一良,神邊貴史

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    Applicant:国立大学法人名古屋大学,大陽日酸株式会社

    Application no:特願2013-185235  Date applied:2013.9

    Country of applicant:Domestic  

    新規原理に基づく実用的トリチウム除去装置及びトリチウム除去方法を考案した

  2. 超臨界二酸化炭素を含む溶液からの溶質の分離方法

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    Application no:2008-162549  Date applied:2008.5

    Country of applicant:Domestic  

  3. *使用済み材料から金または白金族元素を回収する方法

    榎田洋一、澤田佳代、宇留賀和義、菅井 弘

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    Applicant:国立大学法人 名古屋大学、株式会社スリー・アール

    Application no:2008-120014  Date applied:2008.4

    Announcement no:2009-249740 

    Country of applicant:Domestic  

    回収率が高く、大量の化学薬品を要さず、エネルギー消費量を軽減しつつ使用済み材料等から白金族元素や金を回収する。

  4. 置換クロマトグラフィーによるケイ素同位体分離方法

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    Application no:2008-  Date applied:2008

    Country of applicant:Domestic  

  5. 放射性ガス濃度計測装置

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    Application no:平9-61173  Date applied:2007.3

    Country of applicant:Domestic  

  6. 原子炉燃料再処理廃液の処理方法

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    Application no:平8-55906  Date applied:2006.3

    Country of applicant:Domestic  

  7. 使用済み核燃料の処理方法

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    Application no:平7-199531  Date applied:2005.8

    Country of applicant:Domestic  

  8. Method for separating a hydrogen isotope, and apparatus for separating the same hydrogen isotope

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    Application no:10/928,241  Date applied:2004.8

    Country of applicant:Foreign country  

  9. 再処理施設の高レベル廃液処理方法

    藤岡 綱昭、小室 敏也、榎田 洋一、

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    Applicant:三菱原子力工業株式会社

    Application no:平6-52835  Date applied:2004.1

    Announcement no:平7-239396 

    Country of applicant:Domestic  

    【目的】 単純で、合理的な設備となり、併せて、ラフィネート中の残留Pu、U含有量の削減も可能とする高レベル廃液分離回収処理方法を提供すること。
    【構成】使用済燃料を溶解する溶解工程2と、溶解工程2から供給された溶液を主としてU、PuとFPとに分離するPurex法抽出工程3と、Purex法抽出工程3におけるFPを含むラフィネートに含有されるU等の原子価を調整する第1の前処理工程6と、第1の前処理工程6から供給された溶液から主としてU等を抽出する前処理抽出分離工程7と、次に前処理抽出分離工程7から供給された溶液から主としてAm及びCmを抽出するFP-Am等抽出分離工程8と、RE-Am等抽出分離工程11とを含むことを特徴としている。

  10. 水素同位体の分離方法、及び水素同位体の分離装置

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    Application no:2004-20086  Date applied:2004.1

    Country of applicant:Domestic  

  11. 超臨界流体中での金属種の抽出のための超音波で促進されるプロセス原子炉燃料再処理廃液の処理方法

    榎田洋一、C.M. Wai

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    Application no:2003-84231  Date applied:2003.3

    Country of applicant:Domestic  

  12. Ultrasound enhanced process for extracting metal species in supercritical fluids

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    Application no:60/368,029  Date applied:2003.3

    Country of applicant:Foreign country  

  13. 硝酸―リン酸トリブチル(TBP)錯体を含む超臨界二酸化炭素を媒体として用いるウラン廃棄物の除染方法

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    Application no:2001-107227  Date applied:2001.4

    Announcement no:2002-303694 

    Country of applicant:Domestic  

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Teaching Experience (On-campus) 1

  1. Fundamentals of Chemistry I

    2011

 

Social Contribution 4

  1. 原子力エネルギーシステムシンポジウム

    2013.5

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    米国,中国及び日本の原子力有識者,川勝平太静岡県知事,有馬朗人元科学技術庁長官の出席および市民約120名の出席を得て,「トリウム燃料を利用した原子炉開発の課題と展望-」と題する公開シンポジウムを副題「―世界各国および我が国の研究開発状況を知り、今後の課題と展望を探る一」の下で静岡県静岡市にて開催した.

  2. Norning Seminar at Aichi Gakuin University

    Role(s):Appearance, Lecturer

    Aitigakuin University  Morning Seminar  Kusumoto campus of Aichi Gakuin University   2017.6

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    Audience: College students, Graduate students, Teachers, Guardians, Researchesrs, General, Media

    Type:Lecture

    135th Morning Seminar entitled'Worst Radioactive Waste where does spent nuclear fuel go? Did Pandora's box emit only an empty feeling of hope?'

  3. 第29回原子力エネルギーシステム研究委員会公開シンポジウム

    Role(s):Appearance, Panelist, Commentator, Presenter, Chief editor, Planner, Organizing member, Report writing, Contribution

    2021.2

  4. 第28回原子力エネルギーシステム研究委員会公開シンポジウム

    Role(s):Appearance, Commentator, Presenter, Planner, Organizing member

    日本原子力学会中部支部  2021.1

Academic Activities 1

  1. A Board Member of Directors for Atomic Energy Society of Japan

    2016.6