Rodríguez M, Gascón J L, Suárez J A
Instituto Tecnología Nuclear, CIEMAT, Avda. Complutense 22, 28040-Madrid, Spain.
Talanta. 1997 Dec 12;45(1):181-7. doi: 10.1016/s0039-9140(97)00118-5.
This paper describes the experimental studies carried out to determine (238)Pu, (239/40)Pu, (241)Pu, (241)Am, (242)Cm and (244)Cm in samples from nuclear power plants (mainly spent ion exchange resins and evaporator concentrates) using an organophosphorus compound immobilized on an inert support. These materials are commercially available under the name TRU Resin (for Transuranium Specific) from Eichrom Industries, Darien, IL. An attempt is made to develop a rapid, accurate method of analysis, with minimum waste generation. Standard solutions of Pu and Am and one sample of spent ion exchange resin that contains fission, activation products, Pu, Am and Cm were analyzed to study the separation factors and interferences in the measurement of Pu, Am and Cm isotopes.
本文描述了为测定核电站样品(主要是废离子交换树脂和蒸发器浓缩物)中的钚-238、钚-239/40、钚-241、镅-241、锔-242和锔-244所开展的实验研究,该测定使用固定在惰性载体上的有机磷化合物。这些材料以TRU Resin(超铀元素专用)的名称从伊利诺伊州达里恩市的Eichrom Industries公司购得。研究旨在开发一种快速、准确的分析方法,同时将废物产生量降至最低。对钚和镅的标准溶液以及一个含有裂变产物、活化产物、钚、镅和锔的废离子交换树脂样品进行了分析,以研究钚、镅和锔同位素测量中的分离因子和干扰情况。