Determination of trace amounts of plutonium in low-active liquid wastes from spent nuclear-fuel reprocessing plants by flow injection-based solid-phase extraction/electrochemical detection system

フローインジェクション固相抽出/電気化学検出システムによる再処理廃液中の微量プルトニウムの定量

田口 茂郎 ; 山本 昌彦   ; 駿河谷 直樹 ; 黒沢 明; 檜山 敏明; 田中 龍彦*

Taguchi, Shigeo; Yamamoto, Masahiko; Surugaya, Naoki; Kurosawa, Akira; Hiyama, Toshiaki; Tanaka, Tatsuhiko*

A flow injection (FI)-based electrochemical detection system coupled to a solid-phase extraction column was developed for the determination of trace amounts of plutonium in liquid wastes from spent nuclear-fuel reprocessing plants. The relative standard deviation of ten analyses was 1.1% for a plutonium standard solution of 25 g L containing 0.05 g of Pu. The detection limit calculated from three-times the standard deviation was 0.82 g L (1.64 ng of Pu).