KINDAI UNIVERSITY


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ATSUMI Hisao

Profile

FacultyDepartment of Electric and Electronic Engineering / Graduate School of Science and Engineering Research / Atomic Energy Research Institute
PositionVice President
Degree
Commentator Guidehttps://www.kindai.ac.jp/meikan/255-atsumi-hisao.html
URL
Mail
Last Updated :2020/10/09

Education and Career

Education

  •  - 1987 , Osaka University, Graduate School, Division of Engineering
  •  - 1982 , Osaka University, Faculty of Engineering
  •   1978  - 1982 , Osaka University, School of Engineering

Academic & Professional Experience

  •   2008 04 ,  - 現在, Faculty of Science and Engineering, Kindai University
  •   2007 04 ,  - 2008 03 , Faculty of Science and Engineering, Kindai University
  •   1999 04 ,  - 2007 03 , Faculty of Science and Engineering, Kindai University
  •   1995 04 ,  - 1999 03 , Faculty of Science and Engineering, Kindai University
  •   1987 04 ,  - 1995 03 , Faculty of Science and Engineering, Kindai University
  •   1993 ,  - 1994 , Max-Planck-Institute for Metal Research,
  •   1992 , - National Institute for Fusion Science,
  • Collaborating Researcher
  • Guest Scientist

Research Activities

Research Areas

  • Energy, Nuclear engineering
  • Energy, Nuclear fusion
  • Nanotechnology/Materials, Metallic materials
  • Humanities & social sciences, Science education

Research Interests

  • Absorption Properties, Vacuum, Zirconium, Magnesium, Thermoelectric Materials, Hydrogen Storage, Graphite, Carbon, Plasma Facing Materials, Energy Education, Hydrogen, Physical Metallurgy, Nuclear Fusion, Nuclear Power Science

Published Papers

  • Hydrogen absorption/desorption characteristics of Mg-V-Ni hydrogen storage alloys, Tomoya Sakamoto, Hisao Atsumi, Fusion Engineering and Design, Fusion Engineering and Design, 138, 6 - 9, Jan. 2019 , Refereed
  • Retention and release of hydrogen isotopes in carbon materials priorly charged in gas phase, Hisao Atsumi, Yuki Kondo, Fusion Engineering and Design, Fusion Engineering and Design, 131, 49 - 53, Jun. 2018 , Refereed
  • Thermal Desorption of Hydrogen from Carbon and Graphite at Elevated Temperatures, H. Atsumi, Y. Takemura, T. Konishi, T. Tanabe, T. Shikama, Journal of Nuclear Materials, Journal of Nuclear Materials, 438, S963 - S968, Jul. 2013 , Refereed
  • Mechanism underlying Trapping of Hydrogen Isotopes in Neutron-Irradiated Plasma Facing Materials, Y.Hatano, M.Hara, S.Akamaru, K.Zhang, T.Nozaki, H.Kurishita, Y.Nagai, T.Toyama, B.Tsuchiya, A.Hasegawa, S.Nogami, Y.Oya, T.Oda, K.Sato, Y.Ueda, H.Atsumi, T.Muroga, T.Nagasaka, D.Kato, Annual Report of National Institute for Fusion Science April 2010-March 2011, Annual Report of National Institute for Fusion Science April 2010-March 2011, 10, 551, Oct. 2011
  • Neutron Irradiation Effects in Graphite for Fusion Reactor Application -Hydrogen Absorption, Diffusion and Annealing Effects-, H.Atsumi, T.Shikama, KINKEN Research Highlights 2009, KINKEN Research Highlights 2009, 48, Sep. 2009 , Refereed
  • Hydrogen Retention in Graphite and Carbon Material under a Fusion Reactor Environment, H.Atsumi, Journal of Nuclear Materials, Journal of Nuclear Materials, 313-316, 543 - 547, Jan. 2003 , Refereed
  • Concentration Effect on Hydrogen Absorption into Graphite, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 36, 93 - 96, Oct. 2000 , Refereed
  • Hydrogen Retention in Carbonized Tungsten and Molybdenum, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 35, 115 - 119, Sep. 1999 , Refereed
  • Hydrogen-Induced Structural Changes of RFe2 Intermetallic Compounds, H.Atsumi, M.Iseki, M.Hirscher, H.Kronmüller, International Journal of Hydogen Energy, International Journal of Hydogen Energy, 24, 129 - 133, Mar. 1999 , Refereed
  • Structural Changes of RFe2 Intermetallic Compounds by Hydrogenation, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 34, 71 - 75, Sep. 1998 , Refereed
  • Hydrogen Retention in Carbon-Contained Tungsten and Molybdenum, H.Atsumi, T.Tanabe, Proceedings of the 6th Japan-CIS Workshop on Interaction of Fuel Particles with Fusion Materials, Proceedings of the 6th Japan-CIS Workshop on Interaction of Fuel Particles with Fusion Materials, 203 - 208, Apr. 1998
  • Hydrogen Behavior in Carbon-Based Materials and Its Neutron Irradiation Effect, H.Atsumi, M.Iseki, T.Shikama, Journal of Nuclear Materials, Journal of Nuclear Materials, 233-237, 1128 - 1132, Dec. 1996 , Refereed
  • Trapping of Hydrogen in Carbon and Graphite, H.Atsumi, M.Iseki, T.Shikama, 109 - 116, Mar. 1996
  • Interaction of Hydrogen with Radiation Damage in Graphite, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 31, 115 - 122, Oct. 1995 , Refereed
  • Radiation Damage of Graphite-Degradation of Material Parameters and Defect Structures-, T.Tanabe, T.Maruyama, M.Iseki, K.Niwase, H.Atsumi, 29, 428 - 434, Apr. 1995 , Refereed
  • Trapping and Detrapping of Hydrogen in Carbon-Based Materials Exposed to Hydrogen Gas, H.Atsumi, M.Iseki, T.Shikama, Journal of Nuclear Materials, Journal of Nuclear Materials, 212-215, 1478 - 1482, Oct. 1994 , Refereed
  • Interaction of Hydrogen with Defect in Graphite, N.Kangai, T.Tanabe, K.Niwase, H.Atsumi, NIFS-PROC (Proceedings of 2nd International Workshop on Tritium Effects in Plasma Facing Components), NIFS-PROC (Proceedings of 2nd International Workshop on Tritium Effects in Plasma Facing Components), 19, 127 - 134, Aug. 1994
  • Trapping, Detrapping and Diffusion of Hydrogen in Graphite Exposed to Hydrogen Gas, H.Atsumi, M.Iseki, T.Shikama, Proceedings of the 2nd Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Reactor Materials, Proceedings of the 2nd Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Reactor Materials, 130 - 143, Jan. 1994
  • X-ray Diffraction Analysis of Neutron Irradiated Some Graphite Materials」, M.Iseki, H.Atsumi, T.Maruyama, 12, 277 - 281, Mar. 1993
  • Hydrogen Absorption Behavior in Neutron Irradiated Graphite, H.Atsumi, M.Iseki, T.Shikama, UTNL-R (Proceedings of Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Reactor Materials), UTNL-R (Proceedings of Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Reactor Materials), 0293, 194 - 199, Mar. 1993
  • Hydrogen Retention in Graphite -Correlation with the Structure-, M.Iseki, H.Atsumi, T.Maruyama, NIFS-PROC (Proceedings of Japan-US Workshop P196 on High Heat Flux Components and Plasma Surface Interactions for Next Devices), NIFS-PROC (Proceedings of Japan-US Workshop P196 on High Heat Flux Components and Plasma Surface Interactions for Next Devices), 12, 225 - 228, Mar. 1993
  • Hydrogen Solubility and Diffusivity in Neutron Irradiated Graphite, H.Atsumi, M.Iseki, T.Shikama, Journal of Nuclear Materials, Journal of Nuclear Materials, 191-194, 368 - 372, Nov. 1992 , Refereed
  • Hydrogen Absorbing Properties of Graphite for Fusion Reactors, H.Atsumi, M.Iseki, T.Shikama, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 28, 221 - 229, Sep. 1992 , Refereed
  • Metal Compacts for High-Level Radioactive Wastes Fixation, H.Atsumi, Y.Tsuji, T.Tsubaki, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 27, 255 - 263, Sep. 1991 , Refereed
  • Neutron Irradiation Effect on Hydrogen Solubility in Graphite, H.Atsumi, M.Iseki, T.Shikama, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 27, 247 - 254, Sep. 1991 , Refereed
  • Electron Beam Dosimetry Using Photo-Stimulable Phosphor, M.Matsuda, T.Kijima, H.Atsumi, Y.Tsuji, M.Hatada, Proceedings of the 3rd International Conference on Radiation Curing, Proceedings of the 3rd International Conference on Radiation Curing, 540 - 544, Sep. 1991
  • Dissolution and Diffusion of Helium in Graphite, H.Atsumi, T.Yamauchi, M.Miyake, Journal of Nuclear Materials, Journal of Nuclear Materials, 179-181, 227 - 230, May 1991 , Refereed
  • Hydrogen Solubility in Neutron Irradiated Graphite, H.Atsumi, M.Iseki, T.Shikama, NIFS-WS (Proceedings of the Japan-US Workshop P-165 on Critical Topics of PFM/PFC Data for the Next Step Fusion Devices), NIFS-WS (Proceedings of the Japan-US Workshop P-165 on Critical Topics of PFM/PFC Data for the Next Step Fusion Devices), 1, 361 - 366, Feb. 1991
  • Dissolution of Hydrogen and Helium in Graphite, H.Atsumi, M.Iseki, T.Shikama, M.Miyake, Extended Abstracts on International Symposium on Carbon 1990, Extended Abstracts on International Symposium on Carbon 1990, 1, 194 - 197, Nov. 1990
  • Characterization and Heat Generation Behavior on Simulated High Level Radioactive Waste-Metal Compacts, H.Atsumi, Y.Tsuji, T.Tsubaki, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 26, 173 - 180, Sep. 1990 , Refereed
  • Thermal Desorption Measurements of Helium from Graphite Exposed to Helium Gas at High Temperatures, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 26, 181 - 187, 1990 , Refereed
  • Beam Irradiation Experiments, M.Miyake, H.Atsumi, Proceedings of Japan-US Workshop P-134 on Evaluation of Graphite as First Wall Material and Development of First Wall Engineering for Next Large Fusion Devices, Proceedings of Japan-US Workshop P-134 on Evaluation of Graphite as First Wall Material and Development of First Wall Engineering for Next Large Fusion Devices, 298 - 305, Oct. 1989
  • Analysis and Evaluation Methods of Thermal Desorption of Gas Atoms from Solids, H.Atsumi, M.Miyake, Technology Reports of the Osaka University, Technology Reports of the Osaka University, 39, 141 - 151, Oct. 1989 , Refereed
  • Solubility and Diffusivity of Gas Atoms in Graphite, H.Atsumi, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 25, 201 - 208, Sep. 1989 , Refereed
  • Deuterium Solubility and Diffusivity in Graphite, H.Atsumi, M.Miyake, IPPJ-AM-64 (Memoirs of the Cooperative Workshop in Institute of Plasma Physics, Nagoya University), IPPJ-AM-64 (Memoirs of the Cooperative Workshop in Institute of Plasma Physics, Nagoya University), 64, 36 - 47, May 1989
  • Light Ion Beam and Electron Beam Irradiation Experiments and Absorption/Desorption Behavior of Deuterium on Graphite, M.Miyake, H.Atsumi, J.Okamura, P.Son, Interim Report by Fusion First Wall Material Research Group. Nuclear Fusion Research Project. "Overall Characterization of Graphites as Fusion First Wall Material and Evaluation of the Stability against Plasmas", Interim Report by Fusion First Wall Material Research Group. Nuclear Fusion Research Project. "Overall Characterization of Graphites as Fusion First Wall Material and Evaluation of the Stability against Plasmas", 140 - 160, Jan. 1989
  • Thermal Desorption Behavior of He Implanted into Graphite, S.Tokura, H.Atsumi, T.Yamauchi, M.Shinno, S.Yamanaka, M.Miyake, Journal of Nuclear Materials, Journal of Nuclear Materials, 155-157, 246 - 250, Dec. 1988 , Refereed
  • Absorption and Desorption of Deuterium on Graphite at Elevated Temperatures, H.Atsumi, S.Tokura, M.Miyake, Journal of Nuclear Materials, Journal of Nuclear Materials, 155-157, 241 - 245, Dec. 1988 , Refereed
  • Graphite Surface Erosion by Ion Irradiation and Releasing Behavior of Deuterium and Helium from Graphite, Hisao ATSUMI, Osaka University, Osaka University, Dec. 1988 , Refereed
  • Solidification of High-Level Radioactive Wastes by Metal Matrix, H.Atsumi, R.Terai, Y.Tsuji, T.Tsubaki, Journal of the Faculty of Science and Technology Kinki University, Journal of the Faculty of Science and Technology Kinki University, 24, 241 - 248, Sep. 1988 , Refereed
  • Thermal Desorption Measurement of Deuterium from Graphite Exposed to D2 Gas Atmosphere at Elevated Temperatures, H.Atsumi, S.Tokura, M.Miyake, Technology Reports of the Osaka University, Technology Reports of the Osaka University, 37, 255 - 261, Oct. 1987 , Refereed
  • Absorption and Desorption of D2 on Graphite, H.Atsumi, M.Miyake, IPPJ-AM-50 (Proceedings of the Japan-US Workshop P-92 on Plasma Material Interaction/High Heat Flux Data Needs for the Next Step Ignition and Steady State Devices), IPPJ-AM-50 (Proceedings of the Japan-US Workshop P-92 on Plasma Material Interaction/High Heat Flux Data Needs for the Next Step Ignition and Steady State Devices), 50, 273 - 275, May 1987
  • Surface Erosion of Isotropic Graphite by the 20keV Deuterium Ion Irradiation, H.Atsumi, S.Tokura, S.Yamanaka, M.Nunogaki, M.Miyake, Technology Reports of the Osaka University, Technology Reports of the Osaka University, 36, 41 - 46, 1986 , Refereed
  • Releasing Behavior of Tritium from Neutron Irradiated Borosilicate Glass, Y.Yamamoto, K.Kitagawa, H.Atsumi, S.Yamanaka, M.Miyake, Scientific Basis for Nuclear Waste Management, Scientific Basis for Nuclear Waste Management, Ⅵ, 191 - 198, Jan. 1983 , Refereed
  • Thermal Release of Tritium from Neutron Irradiated Glass, M.Miyake, H.Atsumi, Y.Nakamura, S.Yamanaka, Y.Yamamoto, K.Kitagawa, Fusion Technology 1982, Fusion Technology 1982, 1, 555 - 560, Jan. 1983 , Refereed
  • A Method for Determining Tritium Released from Solid Materials, M.Miyake, H.Atsumi, S.Yamanaka, Y.Yamamoto, K.Kitagawa, Technology Reports of the Osaka University, Technology Reports of the Osaka University, 32, 429 - 434, Oct. 1982 , Refereed
  • TRAPPING STATE OF HYDROGEN ISOTOPES IN CARBON AND GRAPHITE INVESTIGATED BY THERMAL DESORPTION SPECTROMETRY, H. Atsumi, T. Tanabe, T. Shikama, FUSION SCIENCE AND TECHNOLOGY, FUSION SCIENCE AND TECHNOLOGY, 67(2), 245 - 249, Mar. 2015 , Refereed
    Summary:Thermal desorption spectrometry (TDS) has been investigated to obtain fundamental information of tritium behavior in graphite and carbon materials especially at high temperatures. 29 brands of graphite, HOPG, glassy carbon and CFC materials charged with deuterium gas are tested up to the temperature of 1735 K with a heating rate of 0.1 K/s. TDS spectra have five peaks at 600-700 K, around 900 K, 1200 K, 1300-1450 K and 1600-1650 K The amounts of released deuterium have been compared with crystallographic parameters derived from XRD analysis. Reduction of tritium retention and inventories are discussed.
  • Desorption of hydrogen trapped in carbon and graphite, H. Atsumi, Y. Takemura, T. Miyabe, T. Konishi, T. Tanabe, T. Shikama, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 442(1-3), S746 - S750, Nov. 2013 , Refereed
    Summary:Thermal desorption behavior of deuterium (D-2) from isotropic graphites and a carbon fiber carbon composite (CFC) charged with D-2 gas has been investigated to obtain information concerning hydrogen recycling and tritium inventory in fusion experimental devices as well as a futuristic fusion reactor. After thermal desorption experiments were conducted at temperatures up to 1740 K, a desorption peak at approximately 1600 K (peak 4) was discovered. This is in addition to the previously known peak at approximately 1300 K (peak 3). Peak 3 can be attributed to the release of deuterium controlled by the diffusion process in a graphite filler grain and peak 4 can be attributed to the detrapping of deuterium released from an interstitial cluster loop edge site. Activation energies of peaks 3 and 4 are estimated to be 3.48 and 6.93 eV, respectively. (C) 2013 Elsevier B. V. All rights reserved.
  • Hydrogen behavior in carbon and graphite before and after neutron irradiation - Trapping, diffusion and the simulation of bulk retention, H. Atsumi, T. Tanabe, T. Shikama, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 417(1-3), 633 - 636, Oct. 2011 , Refereed
    Summary:Bulk hydrogen retention and the mechanisms of hydrogen transport in graphite and carbon materials are summarized in the first half of the paper. From the various data on hydrogen retention, diffusion coefficients, nature of trapping sites and annealing effects, simulation of bulk hydrogen retention is performed. Neutron irradiation tends to increase hydrogen retention approximately 100 times larger than that of unirradiated graphite. (C) 2010 Elsevier B.V. All rights reserved.
  • Bulk hydrogen retention in neutron-irradiated graphite at elevated temperatures, H. Atsumi, T. Tanabe, T. Shikama, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 390-91, 581 - 584, Jun. 2009 , Refereed
    Summary:Bulk hydrogen retention and the analysis of absorption kinetics have been studied on graphite samples irradiated with neutrons at various fluences. There are two kinds of hydrogen trapping sites: interstitial cluster loop edge sites (trap 1) and carbon dangling bonds at edge surfaces of a crystallite (trap 2). Neutron irradiation preferably creates trap 2 sites at lower fluences and trap I sites at higher fluences. The dissociation enthalpy becomes 2-3 times higher for neutron-irradiated samples due to the creation of high energy trapping sites. Absorption kinetics, such as diffusion coefficients and absorption rate constants are strongly affected by neutron irradiation and annealing after irradiation. (C) 2009 Elsevier B.V. All rights reserved.
  • Hydrogen trapping in neutron-irradiated graphite, H. Atsumi, A. Muhaimin, T. Tanabe, T. Shikama, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 386-88, 379 - 382, Apr. 2009 , Refereed
    Summary:Bulk hydrogen retention and the analysis of absorption kinetics have been studied on three brands of graphite irradiated with neutrons at various fluences. Two kinds of hydrogen trapping sites may exist and be additionally produced during irradiation: interstitial cluster loop edge sites (trap 1) and carbon dangling bonds at edge surfaces of crystallites (trap 2). Neutron irradiation preferably creates trap 2 sites at lower fluences and trap 1 sites at a higher fluence above 0.017 dpa. Trap 2 tends to be annealed out at high temperatures, although trap 1 is hardly decreased even at 1873 K. Diffusion coefficients of hydrogen are reduced for 1-2 orders of magnitude after neutron irradiation at 0.047 dpa, although the activation energy of hydrogen diffusion is kept nearly the same level to unirradiated samples. (C) 2008 Elsevier B.V. All rights reserved.
  • Hydrogen absorption into neutron-irradiated graphite and estimation of the trapping effect, H. Atsumi, N. Shibata, T. Tanabe, T. Shikama, PHYSICA SCRIPTA, PHYSICA SCRIPTA, T128, 72 - 75, Mar. 2007 , Refereed
    Summary:Bulk hydrogen retention and the analysis of absorption kinetics have been studied on graphite irradiated with neutrons at various conditions. Two kinds of hydrogen trapping sites may exist and be additionally produced during irradiation: interstitial cluster loop edge sites (trap 1) and carbon dangling bonds at edge surfaces of crystallites (trap 2). Neutron irradiation preferably creates trap 2 sites at lower fluences and trap 1 sites at a higher fluence. Trap 2 tends to be annealed out at high temperatures, although trap 1 is hardly decreased even at 1873 K. The activation energy of hydrogen diffusion is found to be increased from 1.04 to 1.60 eV by neutron irradiation.
  • Hydrogen absorption and transport in graphite materials, H Atsumi, K Tauchi, JOURNAL OF ALLOYS AND COMPOUNDS, JOURNAL OF ALLOYS AND COMPOUNDS, 356, 705 - 709, Aug. 2003 , Refereed
    Summary:Hydrogen absorption and transport in graphite materials have been studied to obtain fundamental information for a fusion reactor application and for hydrogen storage materials. Two kinds of hydrogen trapping sites should exist. One will be carbon dangling bonds located at the edge surface of a crystallite with an adsorption enthalpy of 2.6 eV, the other will be a solitary carbon dangling bond introduced by ion or neutron irradiation, such as an interstitial cluster loop edge, with an enthalpy of 4.4 eV. The results are compared with thermal desorption spectra of deuterium from graphites which were gas charged, ion irradiated and nano-structured by ball milling. These spectra can be well represented with three kinds of desorption process with activation energies of 1.3, 2.6 and 4.4 eV. (C) 2003 Elsevier B.V. All rights reserved.
  • Mechanism of hydrogen trapping and transport in carbon materials, H Atsumi, PHYSICA SCRIPTA, PHYSICA SCRIPTA, T103, 77 - 80, 2003 , Refereed
    Summary:Bulk hydrogen retention and hydrogen diffusion in graphite and carbon materials have been studied to estimate hydrogen recycling and tritium inventory in a fusion reactor environment. Hydrogen may permeate into a filler grain in the form of a hydrogen molecule. diffuse through crystallite boundaries and finally be trapped as hydrogen atoms at the edge surface of a crystallite. In the estimation of hydrogen transport, the activation energy of hydrogen diffusion can be determined from absorption experiments. and the activation energy of detrapping can be obtained from desorption experiments. The activation energies of hydrogen trapping are 2.6eV in ordinary graphite and 4.4eV for irradiated or mechanically milled graphite samples.
  • Hydrogen bulk retention in graphite and kinetics of diffusion, H Atsumi, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 307, 1466 - 1470, Dec. 2002 , Refereed
    Summary:Molecular hydrogen absorption into graphite has been studied in order to obtain information on the 'true' hydrogen diffusion coefficient in graphite, oxygen effect and the mechanism of hydrogen trapping, which should be important issues on estimating hydrogen retention and recycling in plasma facing graphite and CFC. Hydrogen may permeate into a filler grain in the form of hydrogen molecules, diffuse through crystallite boundaries, and may finally be trapped as hydrogen atoms at the edge surface of a crystallite. The diffusion coefficient can be given as D.(m(2)/s) 3.3 x 10(-10)(-1.3 eV/kT), when the trapping effect does not exist. The simulation with mass balance equations can reproduce change of apparent diffusion coefficients. (C) 2002 Elsevier Science B.V. All rights reserved.
  • High thermal conductivity of graphite fiber silicon carbide composites for fusion reactor application, LL Snead, M Balden, RA Causey, H Atsumi, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 307, 1200 - 1204, Dec. 2002 , Refereed
    Summary:The benefits of using CVI SiC/graphite fiber composites as low tritium retaining, high thermal conductivity composites for fusion applications are presented. Three-dimensional woven composites have been chemically vapor infiltrated with SiC and their thermophysical properties measured. One material used an intermediate grade graphite-fiber in all directions (Amoco P55) while a second material used very high thermal conductive fiber (Amoco K-1100) in the high fiber density direction. The overall void was less than 20%. Strength as measured by four-point bending Was comparable to those of SiC/SiC composite. The room temperature thermal conductivity in the high conductivity direction was impressive for both materials, with values >70 W/mK for the P-55 and >420 W/m-K for the K-1100 variant. The thermal conductivity was measured as a function of temperature and exceeds the highest thermal conductivity of CVD SiC currently available at fusion relevant temperatures (>600 degreesC). Limited data on the irradiation-induced degradation in thermal conductivity is consistent with carbon fiber composite literature. (C) 2002 Elsevier Science B.V. All rights reserved.
  • Hydrogen absorption process into graphite and carbon materials, H Atsumi, M Iseki, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 283, 1053 - 1056, Dec. 2000
    Summary:In order to estimate bulk hydrogen retention and recycling in graphite and carbon materials, molecular hydrogen absorption has been studied. Hydrogen absorption rates significantly depend on, samples which arise from grain size, trap concentration and so on. Absorption rate constants differ between the cases of low and high pressures. Trapping has a strong influence, especially in the low pressure range. Oxidation of graphite reduces hydrogen retention and enhances the absorption rate. This suggests that oxygen in graphite does not behave as trapping sites for hydrogen. Activation energies for apparent diffusion for H-2 and D-2 are determined to be 153 and 158 kJ/mol. They are smaller than those energies determined from desorption measurements. (C) 2000 Elsevier Science B.V. All rights reserved.
  • Hydrogen retention in high-Z materials with various contents of carbon, H Atsumi, T Tanabe, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 258, 896 - 901, Oct. 1998 , Refereed
    Summary:In order to estimate hydrogen retention and recycling in high-Z plasma facing components, bulk hydrogen retention in molybdenum and tungsten cct-existing with carbon has been studied. Hydrogen retention in powdered specimens of molybdenum and tungsten is considerably higher than that in sheet specimens due to surface impurities and defects. When molybdenum and tungsten are well carbonized, bulk hydrogen retention is drastically reduced. Coexisting carbon strongly suppresses hydrogen diffusion to reduce absorption rate into the specimen. Ion and neutron irradiation may produce Free carbon to enhance the hydrogen retention in molybdenum and tungsten. (C) 1998 Elsevier Science B.V. All rights reserved.
  • Hydrogen diffusion in DyFe2 and its effect on magnetic properties, H Atsumi, M Hirscher, EH Buchler, J Mossinger, H Kronmuller, JOURNAL OF ALLOYS AND COMPOUNDS, JOURNAL OF ALLOYS AND COMPOUNDS, 231(1-2), 71 - 77, Dec. 1995 , Refereed
    Summary:For the DyFe2 Laves phase intermetallic compound, the nature of hydrogen-induced amorphization, structural changes and the dynamic behavior of hydrogen atoms were studied by means of X-ray diffraction, magnetic after-effect and thermal desorption spectrometry. DyFe2 can be amorphized by hydrogen charging within the narrow temperature range between 523 K and 593 K, even at a low hydrogen pressure of 0.1 MPa. At lower temperatures, DyFe2 forms a crystalline hydride, whereas it decomposes into alpha-Fe and DyH2 at higher temperatures. From the relaxation spectra obtained in magnetic after-effect measurements, it is found that hydrogen atoms in the crystalline hydride occupy the tetrahedral interstitial sites consisting of DyFe3 and Dy2Fe2 with activation energies of short-range diffusion determined as 0.24 eV and 0.35 eV respectively. For the amorphous hydride, hydrogen atoms additionally occupy Dy3Fe sites with an activation energy of 0.43 eV, and the distribution of activation energies becomes broader.
  • Hydrogen-induced structural changes of Fe2Ce alloys, EH Buchler, M Hirscher, H Atsumi, H Kronmuller, JOURNAL OF ALLOYS AND COMPOUNDS, JOURNAL OF ALLOYS AND COMPOUNDS, 231(1-2), 66 - 70, Dec. 1995 , Refereed
    Summary:The amorphization kinetics of the Fe2Ce Laves phase were studied, utilizing X-ray diffraction (XRD), differential scanning calorimetry (DSC) and thermal H desorption measurements. Additionally, the local 1-1 diffusion process in this ferromagnetic compound was investigated by means of magnetic susceptibility and magnetic after-effect (MAE) measurements. Fe2Ce can easily be amorphized (p(H2) = 5 x 10(3) to 1 x 10(5) Pa, T < 400 K); irreversible hydrogen-induced amorphization takes place in a narrow phase boundary which migrates from the surface into the sample. Furthermore, cyclic H-charging of amorphous Fe2Ce below its crystallization temperature reveals a severe degradation in H-storage capacity from 53 at.% to 18 at.% after only three cycles. This degradation is attributed to a hydrogen-induced phase separation into crystalline CeH2 and alpha-Fe which is enhanced by the high mobility of Fe atoms.
  • BULK HYDROGEN RETENTION IN GRAPHITE AT ELEVATED-TEMPERATURE, T TANABE, H ATSUMI, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 209(1), 109 - 112, Mar. 1994 , Refereed
  • THERMAL-DESORPTION OF HELIUM FROM GRAPHITE IRRADIATED BY HE+-IONS, H ATSUMI, S TOKURA, T YAMAUCHI, S YAMANAKA, M MIYAKE, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 141, 258 - 261, Nov. 1986 , Refereed
  • SURFACE EROSION OF GRAPHITE BY D+ IRRADIATION, H ATSUMI, S TOKURA, S YAMANAKA, M NUNOGAKI, M MIYAKE, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 141, 113 - 118, Nov. 1986 , Refereed
  • THERMAL-DESORPTION OF DEUTERIUM AND HELIUM FROM ION IRRADIATED GRAPHITE, H ATSUMI, S YAMANAKA, P SON, M MIYAKE, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 133(AUG), 268 - 271, 1985 , Refereed
  • DIFFUSION ANALYSIS ON THE THERMAL RELEASE OF TRITIUM FROM A NEUTRON ABSORBING MATERIAL, Y YAMAMOTO, H ATSUMI, S YAMANAKA, M MIYAKE, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 120(2-3), 161 - 165, 1984 , Refereed

Conference Activities & Talks

  • TDS measurements and the evaluation of D2 released from graphite, Y.Kondo, H.Atsumi, 18th International Conference on Fusion Reactor Materials (ICFRM-18),   2017 11 09
  • Hydrogen absorption and desorption properties of Mg-Ti-Co alloys synthesized by mechanical alloying, H. Yoshioka, H. Atsumi, 2nd Asia-Pacific Symposium on Tritium Science (APSOT-2),   2017 09 06
  • Hydrogen absorption/desorption characteristics of Mg-V-Ni hydrogen storage allos, T. Sakamoto, H. Atsumi, 2nd Asia-Pacific Symposium on Tritium Science (APSOT-2),   2017 09 06
  • Retention and release of hydrogen isotopes in carbon materials priorly charged in gas phase, H. Atsumi, Y. Kondo, 2nd Asia-Pacific Symposium on Tritium Science (APSOT-2),   2017 09 06
  • Neutron Irradiation Effects on Graphite and Carbon Materials for Fusion Application -Hydrogen Retention and Release-, H. Atsumi, Y. Hatano, K. Niwase, A.Kurumada, T. Shikama, Workshop of TOHOKU University and SCK•CEN at Tokyo,   2015 10 22
  • The Effects of Doping Bismuth on the Thermoelectric Properties of Zn4Sb3, Afiqa Binti Mohamad, Hisao Atsumi, Malaysia-Japan Academic Scholar Conference (MJASC),   2013 11 09
  • Trapping State of Hydrogen Isotopes in Carbon and Graphite Investigated by Thermal Desorption Spectrometry, H. Atsumi, T. Tanabe, T. Shikama, 10th International Conference on Tritium Science and Technology (TRITIUM 2013),   2013 10 22
  • Thermal Desorption of Hydrogen from Carbon and Graphite at Elevated Temperatures, H. Atsumi, Y. Takemura, T. Miyabe, T. Konishi, T. Tanabe, T. Shikama, 20th International Conference on Plasma Surface Interactions (PSI-20),   2012 05 24
  • Desorption of Hydrogen Trapped in Carbon and Graphite, H. Atsumi, Y. Takemura, T. Miyabe, T. Konishi, T. Tanabe, T. Shikama, 15th International Conference on Fusion Reactor Materials (ICFRM-15),   2011 10 17
  • Irradiation Effects on Carbon Materials for Fusion Applications -Structural Changes, Hydrogen Diffusion and Trapping-, H. Atsumi, ICC Workshop on the Current Status and Prospects Collaborations between IMR and SCK/CEN Using BR2,   2009 09 11
  • Hydrogen in Carbon and Graphite -Trapping, Bulk Retention and Diffusion-, H. Atsumi, T. Tanabe, T. Shikama, 14th International Conference on Fusion Reactor Materials (ICFRM-14),   2009 09 07
  • Neutron Irradiation Effects on Carbon Materials for Fusion Applications -Hydrogen Diffusion and Trapping-, H. Atsumi, 2009 Oarai/IMR Research Meeting,   2009 06 26
  • Bulk Hydrogen Retention in Neutron-Irradiated Graphite at Elevated Temperatures, H.Atsumi, A.Muhaimin, T.Tanabe, T.Shikama, 18th International Conference on Plasma Surface Interactions in Controlled Fusion Devices (PSI-18),   2008 05 26
  • Hydrogen Trapping in Neutron-Irradiated Graphite, H.Atsumi, A.Muhaimin, T.Tanabe, T.Shikama, 13th International Conference on Fusion Reactor Materials (ICFRM-13),   2007 12 13
  • Neutron Irradiation Effects of Carbon Materials for Fusion Applications, H.Atsumi, 2007 Oarai/IMR Research Meeting,   2007 09 06
  • Hydrogen Retention in Deposited Surface Layers of a Plasma-Facing Wall Composed of Carbon and Iron, H.Atsumi, A.Muhaimin, N.Shibata, Y.Nakamura, 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications PFMC11,   2006 10 11
  • Hydrogen Absorption into Neutron-Irradiated Graphite and Estimation of Trapping Effect, H.Atsumi, N.Shibata, T.Tanabe, T.Shikama, 11th International Workshop on Plasma-Facing Materials and Components for Fusion Applications PFMC11,   2006 10 10
  • Tri-lemma of Three "E"s; Energy, Economy and Environment, H. Atsumi,   2006 01 23 , 招待有り
  • Tri-lemma of Three "E"s; Energy, Economy and Environment, H.Atsumi,   2004 12 13 , 招待有り
  • Tri-lemma of Three "E"s; Energy, Economy and Environment, ATSUMI Hisao,   2004 02 24 , 招待有り
  • Hydrogen in Graphite -Simulation of Trapping, Detrapping, Recombination and Diffusion-, H. Atsumi, 11th International Conference on Fusion Reactor Materials (ICFRM-11),   2003 12 10
  • Hydrogen behavior in graphite,   2003 09 25
  • Hydrogen Absorption and Transport in Graphite Materials, H.Atsumi, K.Tauchi, International Symposium on Metal-Hydrogen Systems,   2002 09 03
  • Hydrogen Retention in Graphite and Carbon Materials under a Fusion Reactor Environment, H.Atsumi, 15th International Conference on Plasma Surface Interactions in Controlled Fusion Devices,   2002 05 27
  • Mechanism of Hydrogen Trapping and Transport in Carbon Materials, International Workshop on Hydrogen Isotopes in Fusion Reactor Materials,   2002 05 23
  • Hydrogen Bulk Retention in Graphite and the Kinetics of Diffusion, H.Atsumi, 10th International Conference on Fusion Reactor Materials (ICFRM-10),   2001 10 18
  • High Thermal Conductivity Graphite Fiber, Silicon Carbide Composites for Fusion Reactor Application, L.L.Snead, M.Balden, R.A.Causey, H.Atsumi, 10th International Conference on Fusion Reactor Materials (ICFRM-10),   2001 10 18
  • Hydrogen Absorption Process into Graphite and Carbon Materials, H.Atsumi, M.Iseki, 9th International Conference on Fusion Reactor Materials (ICFRM-9),   1999 10 13
  • Hydrogen Retention in High-Z Materials with Various Contents of Carbon, H.Atsumi, T.Tanabe, Eighth International Conference on Fusion Reactor Materials (ICFRM-8),   1997 10 27
  • Hydrogen-Induced Structural Changes of RFe2 Intermetallic Compounds, H.Atsumi, M.Iseki, M.Hirscher, H.Kronmüller, 5th NATO International Conference ,   1997 09
  • Hydrogen Retention in Carbon-Contained Tungsten and Molybdenum, H.Atsumi, T.Tanabe, 6th Japan-CIS Workshop on Interaction of Fuel Particles with Fusion Materials,   1997 09
  • Diffusion of Hydrogen in Crystalline and Amorphous GdFe2 Alloys, H.Atsumi, M.Hirscher, H.Krönmuller, International Symposium on Metal-Hydrogen Systems,   1996 08
  • Hydrogen Behavior in Carbon-Based Materials and Its Neutron Irradiation Effect, H.Atsumi, M.Iseki, T.Shikama, Seventh International Conference on Fusion Reactor Materials,   1995 09
  • Trapping of Hydrogen in Carbon and Graphite, H.Atsumi, M.Iseki, T.Shikama, 4th Japan-CIS Workshop on the Interactions of Fuel Particles with Fusion Reactor Materials,   1995 09
  • Wasserstoffinduzierte Strukturumwandlungen in DyFe2-Legierungen, H.Atsumi, M.Hirscher, E.H.Büchler, J.Mössinger, H.Kronmüller, Deutsche Physikalische Gesellschaft,   1995 03
  • Hydrogen Diffusion in DyFe2 and Its Effect on Magnetic Properties, H.Atsumi, M.Hirscher, E.H.Büchler, J.Mössinger, H.Kronmüller, International Symposium on Metal-Hydrogen Systems,   1994 11
  • Hydrogen-Induced Structural Changes of Fe2Ce Alloys, ATSUMI Hisao, International Symposium on Metal-Hydrogen Systems,   1994 11
  • Radiation Damage of Graphite -Degradation of Material Parameters and Defect Structures-, T.Tanabe, T.Maruyama, M.Iseki, K.Niwase, H.Atsumi, 3rd International Symposium on Fusion Nuclear Technology,   1994 06
  • Hydrogen Trapping in Graphite at High Temperatures, T.Tanabe, H.Atsumi, N.Kangai, K.Niwase, 2nd International Workshop on Tritium Effects in Plasma Facing Components,   1994 05
  • Hydrogen Transport and Trapping Effects in Graphite, H.Atsumi, M.Iseki, T.Shikama, Second Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Materials,   1993 10
  • Trapping, Detrapping and Diffusion of Hydrogen in Graphite Exposed to Hydrogen Gas, H.Atsumi, M.Iseki, T.Shikama, Sixth International Conference on Fusion Reactor Materials,   1993 09
  • X-ray Diffraction Analysis of Neutron Irradiated Some Graphite Materials, H.Atsumi, M.Iseki, T.Shikama, Japan-CIS Workshop on Interactions of Fuel Particles with Fusion Materials,   1992 12
  • Hydrogen Retention in Graphite -Correlation with the Structure-, H.Atsumi, M.Iseki, T.Shikama, Japan-U.S. Workshop on High Heat Flux Components and Plasma Surface Interactions,   1992 11
  • X-ray Diffraction Analysis of Neutron Irradiated Some Graphite Materials, M.Iseki, H.Atsumi, T.Shikama, Japan-U.S. Workshop on High Heat Flux Components and Plasma Surface Interactions,   1992 11
  • Hydrogen Solubility and Diffusivity in Neutron-Irradiated Graphite, H.Atsumi, M.Iseki, T.Shikama, Fifth International Conference on Fusion Reactor Materials,   1991 11
  • Electron Beam Dosimetry using Photo- Stimulable Phosphor, M.Matsuda, T.Kijima, H.Atsumi, Y.Tsuji, M.Hatada, Third International Conference on Radiation Curing,   1991 04
  • Hydrogen Solubility in Neutron Irradiated Graphite, H.Atsumi, M.Iseki, T.Shikama, Japan-U.S. Workshop on Critical Topics of PFM/PFC Data,   1990 12
  • Dissolution of Hydrogen in Graphite, H.Atsumi, M.Iseki, T.Shikama, M.Miyake, International Symposium on Carbon -New Processing and NewApplications-,   1990 11 05
  • Fourth International Conference on Fusion Reactor Materials, H.Atsumi, T.Yamauchi, M.Miyake, Fourth International Conference on Fusion Reactor Materials,   1989 12
  • 使用済バーナブルポイズン中のトリチウムの挙動(Ⅱ)-B4C/Al2O3ペレットからのトリチウム放出試験-,   1989 04
  • Beam Irradiation Experiments, M.Miyake, H.Atsumi, US-Japan Workshop on Evaluation of Graphite as First Wall Material,   1989 02
  • Absorption and Desorption of Deuterium on Graphite at Elevated Temperatures, H.Atsumi, S.Tokura, M.Miyake, Third International Conference on Fusion Reactor Materials,   1987 10
  • Thermal Desorption Behavior of He Implanted into Graphite, H.Atsumi, S.Tokura, M.Miyake, Third International Conference on Fusion Reactor Materials,   1987 10
  • Thermal Desorption of Helium from Graphite Irradiated by He+ Ions, H.Atsumi, S.Tokura, T.Yamauchi, S.Yamanaka, M.Miyake, Second International Conference on Fusion Reactor Materials,   1986 04
  • Surface Erosion of Graphite by D+ Irradiation, H.Atsumi, S.Tokura, S.Yamanaka, M.Nunogaki, M.Miyake, Second International Conference on Fusion Reactor Materials,   1986 04
  • Thermal Desorption of Deuterium and Helium from Ion Irradiated Graphite, H.Atsumi, S.Yamanaka, P.Son, M.Miyake, First International Conference on Fusion Reactor Materials,   1984 12
  • Releasing Behavior of Tritium from Neutron Irradiated Borosilicate Glass, Y.Yamamoto, K.Kitagawa, H.Atsumi, S.Yamanaka, M.Miyake, Materials Research Society 1982 Annual Meeting,   1982 11

Research Grants & Projects

  • Nuclear and Atomic Science Research, Solidification of high-level radioactive wastes
  • International Collaboration, Hydrogen absorption and desorption properties of hydrogen-absorbing alloys and its structural changes
  • Nuclear and Atomic Science Research, Interactions of hydrogen with fusion reactor materials