Method for analyzing content of trace neptunium in high-level discharge liquid

Abstract

The invention belongs to the technical field of post-treatment analysis, and particularly relates to a method for analyzing the content of trace neptunium in high-level discharge liquid. After high-level discharge liquid is diluted to reduce radioactivity, solid-phase extraction separation is carried out twice in a laboratory, neptunium in a sample is effectively separated, and accurate measurement is achieved through alpha energy spectrum. 1AF and 1AW feed liquids are subjected to simple dilution operation in a hot chamber to reduce radioactivity and then are conveyed to an analysis laboratory, trace neptunium is separated by adopting a TEVA resin column, and the content of neptunium is analyzed and measured by adopting an alpha spectrometer. The method is easy and convenient to operate, the accuracy of analysis results is high, and the operation time of experimenters in high-radiation places is greatly shortened.

Description

technical field [0001] The invention belongs to the technical field of post-processing analysis, and in particular relates to a method for analyzing trace neptunium content in a high discharge material liquid. Background technique [0002] The post-treatment production line of the pilot plant needs to analyze the neptunium content to judge the trend of neptunium in the process flow. Therefore, it is extremely important to accurately determine the neptunium content in the process feed liquid for the smooth operation of the neptunium production line. At present, the measurement of neptunium in high discharge liquids such as 1AF and 1AW is to use UTEVA extraction chromatography column to adsorb and elute trace amounts of uranium, neptunium and plutonium in a hot chamber, and transport the separated samples to the graphite post of the analytical laboratory. , and trace neptunium was measured by graphite crystal pre-diffraction method. However, in the actual application process ...

AI Technical Summary

Problems solved by technology

However, in the actual application process of the pilot plant, due to the strong radioactivity of the feed liquid, the sample pretreatment must be performed in a hot chamber. The process of using a manipulator for separation operation takes a long time and is difficult to operate. The failure rate of the manipulator increases. High labor intensity and long exposure time

Moreover, due to the change of the feed liquid, the graphite post often has samples smaller than the lower limit of measurement, and it is impossible to accurately measure the trace neptunium content in 1AF and 1AW samples.

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