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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 田口 茂郎駿河谷 直樹佐藤 宗一黒沢 明綿引 優檜山 敏明
- Publication Date
- 2006-06
- Publication Date (W3CDTF)
- 2006
- Alternative Title
- Determination of plutonium in highly radioactive liquid waste by spectrophotometry using neodymium as an internal standard for safeguards analysis; Japan Support Program for Agency Safeguards (JASPAS), JC-19
- Periodical title
- JAEA-Technology 2006-041
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NAWe have developed a method of spectrophotometric determination of plutonium ($>$10$^{-4}$ M) in highly radioactive liquid waste for safeguards verification analysis. The method offers reduced sample preparation and analysis time compared to isotope dilution mass spectrometry. It uses neodymium as an internal standard, which allows for determining an index for the authentication of the analytical scheme and the inspection procedure. The relative expanded uncertainty of the repeated analysis (n = 5) was 8.9 \% (coverage factor k = 2) for a highly radioactive liquid waste sample(173 mgL$^{-1}$). The determination limit was calculated to be 6 mgL$^{-1}$ (ten fold's the standard deviation). This method was validated through comparison experiments with isotope dilution mass spectrometry. The analytical results of plutonium in highly radioactive liquid waste using this method were in good agreement with those obtained using isotope dilution mass spectrometry. It is to be noted that the neodymium standard is intended to be provided by the inspector so that an inspector can check the instrument conditions as well as the analytical scheme. The proposed method was successfully applied for the independent on-site safeguards analysis at the Tokai Reprocessing Plant.東海再処理施設において、使用済み核燃料を再処理する際に発生する高放射性廃液中に含まれる、微量プルトニウム($>$10$^{-4}$M)の核物質管理のための分析法として、ネオジムを内標準物質とした吸光光度法による定量手法を開発した。本法は、測定試料に内標準物質のネオジムを既知量添加した後、プルトニウムをPu(VI)に酸化し、Nd(III)とPu(VI)の吸光度比とモル吸光係数比の関係からプルトニウム濃度を算出するものである。本法で用いるネオジムは、内標準物質として用いるほか、測定装置の健全性を確認する指標としても活用できる。さらに本法は、比較的迅速な測定が可能であることから、保障措置上の適時性を確保できることが特徴である。プルトニウム濃度が173mgL$^{-1}$の高放射性廃液試料に対する評価として、分析結果の相対拡張不確かさ(n=5)は8.9\%(包含係数2)であり、定量下限は6mgL$^{-1}$(10$\sigma$)であった。また、本法と同位体希釈質量分析法による比較分析を行った結果、両者の分析値は良好に一致し、東海再処理施設において査察側が現場で行う高放射性廃液中のプルトニウムの検認分析法として適用が可能であることを確認した。
- Source
- /JAEA-Technology-2006-041.pdf （fulltext）