Device for measuring americium and cesium in aftertreatment feed liquid

Abstract

The invention relates to the technical field of nuclear fuel aftertreatment and particularly discloses a device for measuring americium and cesium in aftertreatment feed liquid. A NaI detector is arranged in an area defined by central holes of a lead sheath A, a lead sheath B and a lead sheath D, and a connecting line of the NaI detector penetrates out of a slot in the lead sheath B to be connected with a multi-channel spectrometer; the multi-channel spectrometer is connected with a computer through a data line; and gamma ray signals are converted into electric signals by the NaI detector, theelectric signals are screened by the multi-channel spectrometer and then transmitted into the computer, and automatic sample measuring is realized. The device can effectively shield interference of environmental gamma rays in a measuring system, the multi-channel spectrometer is utilized, thus the gamma radioactivity concentrations of cesium-137 and americium-241 can be measured simultaneously, and the measuring result is directly read by software.

Description

technical field [0001] The invention belongs to the technical field of nuclear fuel post-processing, and in particular relates to a measuring device for americium and cesium in post-processing feed liquid. Background technique [0002] The gamma radioactive activity concentration measurement device in the process feed liquid currently used in the nuclear fuel field includes well-shaped lead chambers, sodium iodide probes, calibrator and other components. This device has the following problems: (1) This device can only measure cesium- 137 gamma activity concentration; (2) The device uses a calibrator to count, and the probe high voltage, magnification, threshold and other parameters need to be manually adjusted, and the adjustment method is extremely cumbersome. Can display counting; (3) NaI detector crystal cross-section is small, and the detection efficiency is less than 5%; (4) The detector is installed in a well-shaped lead chamber, which is prone to pollution during oper...

AI Technical Summary

Problems solved by technology

[0002] The gamma radioactive activity concentration measurement device in the process feed liquid currently used in the nuclear fuel field includes well-shaped lead chambers, sodium iodide probes, calibrator and other components. This device has the following problems: (1) This device can only measure cesium- 137 gamma activity concentration; (2) The device uses a calibrator to count, and the probe high voltage, magnification, threshold and other parameters need to be manually adjusted, and the adjustment method is extremely cumbersome. Can display counting; (3) NaI detector crystal cross-section is small, and the detection efficiency is less than 5%; (4) The detector is installed in a well-shaped lead chamber, which is prone to pollution during operation, and it is difficult to decontaminate; (5) Lead chamber Insufficient thickness and samples with high total gamma radioactivity will have a great influence on the measurement results when placed near the measuring instrument, and the samples must be transferred to other rooms to eliminate the influence

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