Conference

8. Plasma Conference 2014
November 11-18, 2014, TOKI MESSE Niigata Convention Center, Niigata, Japan

♦ 19PA-012 : Tritium Retention in Stainless Steel Pre-irradiated with Helium

M. Matsuyama, S. Abe (Univ. of Toyama)

♦ 19PA-018 : Surface morphology change and sputtering of F82H reduced activation ferritic/martensitic steel and Fe by low-energy high-flux deuterium plasma

Y. Hatano (Univ. of Toyama)

♦ 21pE-4:Tritium release from Inconel 625

Y. Torikai, K. Kobayashi, M. Saito, N. Miya, Y. Ikeda (Univ. of Toyama)

7. International Toki Conference (ITC-24)
November 4-7, 2014, Ceratopia Toki, Toki-city, Gifu, Japan

♦ P4-52: Tritium Retention in Stainless Steel Pre-irradiated with Helium

S. Abe (Univ. of Toyama)

6. 12th Japan-China Symposium on Materials for Advanced Energy Systems and Fission & Fusion Engineering
September 17-20, 2014, Shizuoka, Japan

♦ 105: Influence of He ion seeding into hydrogen isotope plasmas on the hydrogen isotope behaviour in tungsten

V. Kh. Alimov (Univ. of Toyama)

♦ 116: Diffusion and desorption behavior of hydrogen isotopes implanted into copper by glow discharge

K. Noborio (Univ. of Toyama)

♦ 124: Radioactivity measurement by liquid scintillation counter with modified integral counting method

M. Hara (Univ. of Toyama)

♦ 130: Non-destructive measurement of near-surface tritium depth profile in solid by imaging plate

K. Ami (Univ. of Toyama)

♦ 139: Evaluation of concentration distributions of tritium on divertor and wall tiles used in fusion devices using combination of imaging plate technique and β-ray induced X-ray spectrometry

K. Yumizuru (Univ. of Toyama)

♦ 145: Influence of Re addition on hydrogen isotope retention in tungsten

Y. Hatano (Univ. of Toyama)

♦ 146: Apparent tritium solubility in Fusion Reactor Materials

Y. Torikai (Univ. of Toyama)

♦ 154: Research Activity on Tritium-Material Interactions in Hydrogen Isotope Research Center (HRC)

M. Matsuyama (Univ. of Toyama)

5. 14th International Symposium on Metal-Hydrogen Systems
July 20-25, 2014, Hosted by the University of Salford at The Lowry, Salford Quays

♦ TuP-052 A6: Sensing of hydrogen in gas phase using ferromagnetic Pd-Co alloy

S. Akamaru (Univ. of Toyama)

4. Korea-Japan Tritium Joint Workshop
July 14-16, 2014, NFRI (Daejeon)

♦ T8-JA4: Thermal desorption behavior of hydrogen isotopes implanted by glow discharge

M. Matsuyama (Univ. of Toyama)

♦ TI0-JA5: Non-destructive measurement of tritium depth profiles in materials using imaging plate technique

Y. Hatano (Univ. of Toyama)

3. 12th International Workshop on Hydrogen Isotopes in Fusion Reactor Materials (HWS2014)
June 2 - 4, 2014, University of Toyama, Toyama, Japan

♦ 2-AM-8: Surface Morphology of F82H Reduced Activation Ferritic/Martensitic Steel Exposed to High Flux Deuterium Plasma

Y. Hatano*, V. Kh. Alimov, N. Yoshida, H. Watanabe, M. Oyaidzu, T. Hayashi

♦ 2-PM-1: Deuterium Retention in Reduced Activation Ferritic Martensitic Steels Exposed to D Plasmas and Irradiated with D Ions

V. Kh. Alimov*, Y. Hatano, J. Roth, K. Sugiyama, M. Oyaidzu, M. Baldwin, R. Doerner, M. H. J.'t Hoen, H. T. Lee, Y. Ueda, M. Matsuyama, T. Hayashi

2. 21st International Conference on Plasma Surface Interactions in Controlled Fusion Devices (21st PSI)
May 26 - 30, 2014, Ongaku-do, Kanazawa, Japan

♦ P1-096: Retention and Desorption of Hydrogen and Helium from Stainless Steel Exposed to Plasmas of LHD

N. Yoshida, Y. Kimura^a, H. Harada^a, N. Yugami^a, T. Fujiwara, K. Araki, R. Yoshihara, H. Watanabe, M. Tokitani ^b, S. Masuzaki^b, Y. Hatano^c, Y. Oya, ^dK. Okuno^d, (Research Institute for Applied Mechanics, Kyushu Univ, ^aGSES, Kyushu Univ., ^bNIFS, ^cUniv. Toyama, ^dShizuoka Univ.)

♦ P2-057: Influence of Helium on Hydrogen Isotope Exchange in Tungsten at Sequential Exposures to Deuterium and Helium-Protium Plasmas

N.P. Bobyr^a, V.Kh. Alimov,^{b, c}, B.I. Khripunov^a, A.V. Spitsyn^a, Y. Hatano^b, A.V. Golubeva^a, V.B. Petrov^a, (^aNRC 'Kurchatov Institute', ^bHydrogen Isotope Research Center, University of Toyama, ^cMax-Planck-Institut für Plasmaphysik, EURATOM Association)

♦ P2-065: Tritium retention and release properties in polycrystalline tungsten

Y. Nobuta, Y. Yamauchi, T. Hino, Y. Hatano^a, S.Abe^a, M. Matsuyama^a(Laboratory of Plasma Physics and Engineering, Hokkaido University, ^aHydrogen Isotope Research Center, University of Toyama)

♦ P3-018: 2D tritium distribution on tungsten and beryllium tiles used in JET ITER-like wall project

Y. Hatano^a, A. Widdowson, N. Bekris, C. Ayres, A. Baron-Wiechec, J. Likonen^b, S. Koivuranta^b, J. Ikonen^c, and JET EFDA contributors^* (JET-EFDA, Culham Science Centre, ^aUniversity of Toyama,^bVTT, Association Euratom-Tekes, ^cUniversity of Helsinki, ^* See the Appendix of F. Romanelli et al., Proceedings of the 24th IAEA Fusion Energy Conference)

♦ P3-020: Surface modifications of RAFM steels by deuterium exposure: Variation from coral-like/fuzz-like to blister-like features

M. Balden^a, S. Elgeti^a, V.Kh. Alimov^a,b, K. Sugiyama^a, J. Roth^a, O. Ogorodnikova^a, G. Matern^a, H. Maier^a, Y. Hatano , M. Oyaidzu, T. Yamanishi^c, T. Hayashi^d, H.T. Lee^e, Y. Ueda^e, M.H.J 't Hoen^f, G. De Temmerman^f, M. Rasinski^g, E. Fortuna-Zalesna^g, K.J. Kurzydlowski^g, R.P. Doerner^h, M.J. Baldwin^h, (^aMax-Planck-Institut fur Plasmaphysik, EURATOM Association, ^bHydrogen Isotope Research Center, University of Toyama, ^c Tritium Technology Group, Japan Atomic Energy Agency, ^dTritium Technology Group, Japan Atomic Energy Agency, ^eGraduate School of Engineering, Osaka University, ^fDutch Institute for Fundamental Research, ^gWarsaw University of Technology, Faculty of Material Science and Engineering, ^fCenter for Energy Research, University of California)

♦ P3-037: Surface morphology and deuterium retention in tungsten and tungsten-rhenium alloy exposed to low-energy, high flux D plasma

V.Kh. Alimov^a, Y. Hatano^a, K. Sugiyama^b, M. Balden^b, S. Elgeti^b, M. Oyaidzu^c, S. Akamaru^a, T. Hayashi^d, M. Matsuyama^a (^aHydrogen Isotope Research Center, University of Toyama, ^bMax-Planck-Institut für Plasmaphysik, EURATOM Association, ^cTritium Technology Group, Japan Atomic Energy Agency, ^dTritium Technology Group, Japan Atomic Energy Agency)

♦ P3-038: Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten

M. Shimada¹, M. Hara², T. Otsuka³, Y. Oya⁴, Y. Hatano² (¹Fusion Safety Program, Idaho National Laboratory, ²Hydrogen Isotope Research Center, University of Toyama, ³Kyushu University, Interdisciplinary Graduate School of Engineering Science, ⁴ Radioscience Research Laboratory, Faculty of Science, Shizuoka University)

P3-050: Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-damaged tungsten

C.N. Taylor^a, M. Shimada^a, B. Merrill^a, D.W. Akers^b, Y. Hatano^c (^aFusion Safety Program, Idaho National Laboratory, ^bExperimental Programs, Idaho National Laboratory, ^cHydrogen Isotope Research Center, University of Toyama)

♦ P3-111: Retention and Desorption of Hydrogen in Plasma Facing Wall of QUEST

N. Yugami, N. Yoshida ^a, T. Fujiwara ^a, K. Araki ^a, R. Yoshihara ^a, H. Watanabe ^a, K. Hanada^a, H. Zushi^a, Y. Hatano^b, Y. Oya^cK. Okuno^d(GSES, Kyushu Univ., ^aRIAM, Kyushu Univ., ^bUniv. Toyama, ^cShizuoka Univ.

1. 9th Japan-Korea Workshop on Fusion Material Technology Toward Next Fusion Devices
February 7, 2014, Hokkaido University, Sapporo, Japan

♦ Release behavior of tritium from stainless steel exposed to plasma experiments in LHD

M. Matsuyama (University of Toyama)
[Hydrogen Isotope Research Center, University of Toyama]

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