Determination of tritium concentration in fuel reprocessing liquid waste by vacuum freeze distillation.

スポンサーリンク

概要

• 論文の詳細を見る

• The vacuum freeze distillation method was successfully applied to the preparation of radiochemically pure water samples used for determining the tritium concentration in highly radioactive liquid waste produced in nuclear fuel reprocessing.<BR>This method yielded a decontamination factor exceeding 10<SUP>5</SUP> for radioruthenium and other long-lived fission products. The isotope effect on the tritium concentration was corrected by applying an enrichment factor determined from experiment.<BR>A small portion of the high level liquid waste solution was taken from the Repro-cessing Plant of the Japan Atomic Energy Research Institute, neutralized with 2 N sodium hydroxide, and subjected to the vacuum freeze distillation. The distillate was subsequently analyzed for tritium by liquid scintillation counting. The tritium concen-tration in the waste solution was found to be approximately 0.13 μCi/m/, which corre-sponded to about 70% of the total tritium contained in the original spent fuel rods.

• 一般社団法人 日本原子力学会の論文

著者

• TACHIMORI Syoichi

  Japan Atomic Energy Research Institute

関連論文

• Preliminary Study on Production of Xenon-133 from Neutron-Irradiated Uranium Metal and Oxides by Oxidation
• Determination of tritium concentration in fuel reprocessing liquid waste by vacuum freeze distillation.

スポンサーリンク