Iwakiri Hirotomo

写真a

Title

Professor

Researcher Number(JSPS Kakenhi)

80325480

Current Affiliation Organization 【 display / non-display

  • Duty   University of the Ryukyus   Faculty of Education   Elementary and Secondary School Teacher Training Program   Professor  

Academic degree 【 display / non-display

  • Kyushu University -  Doctor of Engineering

External Career 【 display / non-display

  • 2000.04
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    2007.03

    Research Institute for Applied Mechanics Kyushu University, Research Associate  

  • 2007.04
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    2008.03

    Research Institute for Applied Mechanics Kyushu University, Assistant Professor  

  • 2008.04
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    2016.03

    University of the Ryukyus, Faculty of Education, Associate Professor  

  • 2008.04
    -
    2016.03

    University of the Ryukyus, Faculty of Education, Associate Professor  

  • 2016.04
     
     

    University of the Ryukyus, Faculty of Education, Professor  

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Affiliated academic organizations 【 display / non-display

  •  
     
     
     

    Society of Japan Science Teaching 

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    The Japan Institute of Metals 

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    The Japan Society of Applied Physics 

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    The Japan Society of Plasma Science and Nuclear Fusion Research 

  • 1996.04
    -
    Now
     

    The Japan Institute of Metals 

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Research Interests 【 display / non-display

  • Lattice Defect,Computer simulation,quantum beam,Physics Education,Nuclear Fusion

  • quantum beam

  • Computer simulation

  • Physics Education

  • Lattice Defect

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Research Areas 【 display / non-display

  • Energy Engineering / Nuclear fusion

  • Natural Science / Magnetism, superconductivity and strongly correlated systems

  • Nanotechnology/Materials / Nanomaterials

  • Physical properties II

  • Nuclear fusion studies

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Published Papers 【 display / non-display

  • Effect of uniaxial tensile strain on binding energy of hydrogen atoms to vacancy-carbon-hydrogen complexes in α-iron

    Hirayama S.

    Nuclear Materials and Energy ( Nuclear Materials and Energy )  31   2022.06 [ Peer Review Accepted ]

    Type of publication: Research paper (scientific journal)

  • Interaction of primary precipitates in reduced -activation ferritic/martensitic steel F82H with hydrogen atoms: Atomistic calculation based on the density functional theory

    Iwakiri H.

    Nuclear Materials and Energy ( Nuclear Materials and Energy )  31   2022.06 [ Peer Review Accepted ]

    Type of publication: Research paper (scientific journal)

  • Hydrogen retention behavior of primary precipitates in F82H steel: Atomistic calculation based on the density functional theory

    Watanabe Y.

    Fusion Engineering and Design ( Fusion Engineering and Design )  159   2020.10 [ Peer Review Accepted ]

    Type of publication: Research paper (scientific journal)

  • Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond

    Nozawa T.

    Journal of Nuclear Materials ( Journal of Nuclear Materials )  511   582 - 590   2018.12 [ Peer Review Accepted ]

    Type of publication: Research paper (scientific journal)

     View Summary

    © 2018 Elsevier B.V. The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the application of SiC/SiC composites as functional structure to be used in the dual coolant breeding blanket concept. This paper aims to summarize previous 10-years activities of the R&D of Japan and to provide the key deliverables toward the DEMO design. In Task-1, good creep and fatigue durability were first demonstrated. Besides, in-plane and inter-laminar strength anisotropy maps at elevated temperatures were comprehensively identified. In parallel, the irradiation effects of SiC materials were specifically determined as input parameters of the analytical model to provide for the irradiation-induced residual stresses. In Task-2, the apparent dose-dependence of the radiation-induced electrical conductivity and the indicative radiation-induced electrical degradation was identified by various irradiation sources. In addition, good gas confinement was identified. Furthermore, no accelerated corrosion for duration of 3000 h at below 1173 K was first demonstrated. With these achievements, it is suggested that the in-vessel component technology, e.g., material corrosion database development, activated corrosion product evaluation code development, compact module tests for validation of the key functions of the components, technology integration assessment for fusion nuclear tests, etc., should be further developed toward DEMO in near-term.

  • Hydrogen retention behavior of beryllides as advanced neutron multipliers

    Fujii Y.

    Nuclear Materials and Energy ( Nuclear Materials and Energy )  9   233 - 236   2016.12 [ Peer Review Accepted ]

    Type of publication: Research paper (scientific journal)

     View Summary

    © 2016 The Authors Beryllium intermetallic compounds (beryllides) are the most promising candidate materials for use as advanced neutron multipliers in future fusion reactors because of their low swelling and high stability at high temperatures. Recently, beryllium–titanium beryllide pebbles such as Be12Ti have been successfully fabricated using a novel granulation process. In this study, the fundamental aspects of the behavior of hydrogen isotopes in Be12Ti pebbles were investigated via thermal desorption spectroscopy and transmission electron microscopy. In addition, atomistic calculations using first principles electronic-structure methods were applied to determine the solution energy of hydrogen in Be12Ti. The results showed simpler and weaker hydrogen-trapping efficiency for Be12Ti than for pure Be.

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