溶媒抽出法による原子炉級酸化トリウムの製錬

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  • 金子 修
    三井金属鉱業株式会社中央研究所製煉化学研究室

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タイトル別名
  • Solvent Extraction Process for Preparing Reactor Grade ThO<SUB>2</SUB>
  • ヨウバイ チュウシュツホウ ニ ヨル ゲンシロキュウ サンカ トリウム ノ セイレン

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抄録

A semi-pilot plant by T. B. P.solvent extraction process was constructed to study several process variables in controllng impurity content and particle sizes of ThO2 for nuclear use.<BR>The results obtained are as follows:<BR>(1) Mnch care should be taken to adjust the concentration of thorium as well as the acidity in feed solution. High thorium and nitric acid concentration gave best results.<BR>Scrubbing stage was also important. Use of high nitric, acid solution in a small ratio was necessary to obtain high purity ThO2.<BR>(2) A typical analysis of the purified ThO2 was as follows: Gd, Sm, Eu, Dy, Nd, Pr, La and Ce, were less than 0.25 ppm respectively, B was less than 0.25 ppm, Fe, Cu, Mg and Mn were less than 2.5 ppm respectively.<BR>(3) Particle sizes of the products could be controlled to give <1 micron to several microns by selecting the conditions to prepare the preceding thorium oxalate precipitates.<BR>(4) The reactor grade ThO2 plant could run economically on its semi-pilot plant basis (several hundred kgs of ThO2 per month).

収録刊行物

  • 日本鑛業會誌

    日本鑛業會誌 77 (874), 265-270, 1961

    一般社団法人 資源・素材学会

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