低レベル放射性廃棄物の溶融固化体に含まれるThとUの分析へのUTEVAレジンカートリッジの適用

Application of UTEVA resin cartridge to separate Th and U in solidified products of low-level radioactive waste

藤原 亜佐子 ; 亀尾 裕 ; 中島 幹雄

Fujiwara, Asako; Kameo, Yutaka; Nakashima, Mikio

低レベル放射性廃棄物を模擬して溶融固化体を作製し、それを酸分解した溶解液を用いてUTEVAレジンによるThとUの分離試験を行った。また、NpとPu, Amの溶出挙動もおさえた。カラムシステムでは流速をコントロールできず、まれに流速が低下したため、UTEVAレジンカートリッジと送液ポンプを用いて流速を100ml/hにコントロールして分離試験を行ったところ、ThとUは溶融固化体主成分から分離されることを確認した。

Separation of Th and U in dissolved solution of solidified products of simulated waste with UTEVA resin has been investigated. Thorium and U were separated from the other elements such as Na, Al, Ca, Fe by column chromatography with UTEVA resin and recovered with the solution containing 0.1 M HNO and 0.05 M oxalic acid. The concentration of Am and Pu in the fraction to recover Th and U was under the detection limit. Although 1% of Np was contaminated to the recovery fraction of Th and U, Np would not interfere the measurement of U. UTEVA resin cartridge system with flow pomp was applied to the separation of Th and U. The result from cartridge system showed good separation of Th and U from Na, Al, Ca, and Fe. The flow rate with cartridge system was 4-5 times faster than that with column system to shorten the operation time.