放射性テルル（<SUP>127m</SUP>Te-<SUP>127</SUP>Te）によるZr-Te合金の酸化機構の研究

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書誌事項

タイトル別名
  • Study on the Oxidation Mechanism of Zr-Te Alloy by Radioactive Tellurium (Studies on the Oxidation of Zirconium and its Alloys, 3rd Report)
  • 放射性テルル(127mTe-127Te)によるZr-Te合金の酸化機構の研究
  • ホウシャセイ テルル 127mTe-127Te ニ ヨル Zr-Te ゴウキン ノ サンカ キコウ ノ ケンキュウ

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抄録

The oxidation phenomena of Zr-Te alloy were studied using the tracer technique. Small amounts (0.1∼0.3%) of 127mTe-127Te, whose specific activity was about 5 mc/g, were added to pure reactor grade zirconium sheets by diffusion at 950°C. The alloy specimens thus obtained were oxidized in air or heated in vacuo at 750°C for 30 hrs. Measurements of the activity from the specimen surface with a G.M. counter showed that zirconium oxide formed by the oxidation treatment contained almost the same quantity of tellurium as the zirconium alloy. By separate counting of internal conversion electron from the 127mTe and β-ray from the 127Te using a 13.6 mg/cm2 aluminum absorber, we observed that the surface concentration of tellurium was raised markedly by annealling in vacuo, but not by oxidation in air. It is concluded that tellurium is far less movable in the oxide than in the zirconium alloy, suggesting that tellurium ions are trapped by oxygen-ion vacancies in the zirconium oxide. This trapping action, at the same time, decreases the mobility of the oxygen-ion vacancies. The good oxidation resistance of Zr-Te alloy is explained by this mechanism.

収録刊行物

  • 日本金属学会誌

    日本金属学会誌 26 (4), 267-270, 1962

    公益社団法人 日本金属学会

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