Thermomigration of tritium in V-4Cr-4Ti alloy

Kenichi Hashizume, Kazuhiro Ogushi, Teppei Otsuka, Tetsuo Tanabe

    Research output: Contribution to journalArticle

    3 Citations (Scopus)

    Abstract

    In order to obtain heat of transport, Q*, of tritium in V-4Cr-4Ti alloy (NIFS-HEAT-2), thermomigration experiments have been carried out at a temperature ranging from 333 to 471 K. Tritium homogeneously distributed in the specimen bar was forced to migrate by an applied temperature gradient. The resulting tritium profile was visualized by an imaging plate technique and Q* was determined from the profile according to a thermomigration theory. The obtained value of Q* was about +20 kJ/mol for the initial hydrogen concentration of 0.008 at.%, and no appreciable temperature dependence was observed. In order to examine the effect of thermomigration on tritium retentions in pure V and the alloy used as cooling tubes or first walls of the blanket, a simple model calculation was made under designed temperature gradients in fusion reactors. The result showed that tritium retention could be enhanced about 10-20% compared with the case without thermomigration.

    Original languageEnglish
    Pages (from-to)1175-1178
    Number of pages4
    JournalJournal of Nuclear Materials
    Volume417
    Issue number1-3
    DOIs
    Publication statusPublished - Oct 1 2011

    Fingerprint

    thermomigration
    Tritium
    tritium
    Thermal gradients
    temperature gradients
    fusion reactors
    blankets
    Fusion reactors
    profiles
    Hydrogen
    tubes
    Cooling
    cooling
    Imaging techniques
    heat
    Temperature
    temperature dependence
    hydrogen

    All Science Journal Classification (ASJC) codes

    • Nuclear and High Energy Physics
    • Materials Science(all)
    • Nuclear Energy and Engineering

    Cite this

    Thermomigration of tritium in V-4Cr-4Ti alloy. / Hashizume, Kenichi; Ogushi, Kazuhiro; Otsuka, Teppei; Tanabe, Tetsuo.

    In: Journal of Nuclear Materials, Vol. 417, No. 1-3, 01.10.2011, p. 1175-1178.

    Research output: Contribution to journalArticle

    Hashizume, Kenichi ; Ogushi, Kazuhiro ; Otsuka, Teppei ; Tanabe, Tetsuo. / Thermomigration of tritium in V-4Cr-4Ti alloy. In: Journal of Nuclear Materials. 2011 ; Vol. 417, No. 1-3. pp. 1175-1178.
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    abstract = "In order to obtain heat of transport, Q*, of tritium in V-4Cr-4Ti alloy (NIFS-HEAT-2), thermomigration experiments have been carried out at a temperature ranging from 333 to 471 K. Tritium homogeneously distributed in the specimen bar was forced to migrate by an applied temperature gradient. The resulting tritium profile was visualized by an imaging plate technique and Q* was determined from the profile according to a thermomigration theory. The obtained value of Q* was about +20 kJ/mol for the initial hydrogen concentration of 0.008 at.{\%}, and no appreciable temperature dependence was observed. In order to examine the effect of thermomigration on tritium retentions in pure V and the alloy used as cooling tubes or first walls of the blanket, a simple model calculation was made under designed temperature gradients in fusion reactors. The result showed that tritium retention could be enhanced about 10-20{\%} compared with the case without thermomigration.",
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    AU - Ogushi, Kazuhiro

    AU - Otsuka, Teppei

    AU - Tanabe, Tetsuo

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    AB - In order to obtain heat of transport, Q*, of tritium in V-4Cr-4Ti alloy (NIFS-HEAT-2), thermomigration experiments have been carried out at a temperature ranging from 333 to 471 K. Tritium homogeneously distributed in the specimen bar was forced to migrate by an applied temperature gradient. The resulting tritium profile was visualized by an imaging plate technique and Q* was determined from the profile according to a thermomigration theory. The obtained value of Q* was about +20 kJ/mol for the initial hydrogen concentration of 0.008 at.%, and no appreciable temperature dependence was observed. In order to examine the effect of thermomigration on tritium retentions in pure V and the alloy used as cooling tubes or first walls of the blanket, a simple model calculation was made under designed temperature gradients in fusion reactors. The result showed that tritium retention could be enhanced about 10-20% compared with the case without thermomigration.

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