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Automatic mass total gamma analyzer system

An analyzer and gamma analyzer technology, applied in the direction of instrumentation, radiation measurement, X-ray energy spectrum distribution measurement, etc., can solve the problems of consuming manpower and material resources, high analysis frequency, and many analysis points, so as to improve work efficiency, Simple analysis process, reducing the effect of received dose

Active Publication Date: 2020-05-19
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology

In the whole process, the total gamma measurement is one of the most important analysis items. It has the characteristics of many analysis points and high analysis frequency. At present, the gamma counting method is generally used for measurement. The extraction and other operations are all done manually, which requires a lot of manpower and material resources. The labor intensity of the staff is high, the efficiency is low, and there is also the risk of excessive radiation doses.

Method used

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Embodiment Construction

[0026] The present invention will be further described below in conjunction with the accompanying drawings and embodiments.

[0027] Such as figure 1 As shown, an automatic large amount of total gamma analyzer system provided by the present invention is used to measure the gamma rays of the radioactive sample to be tested in the sample distribution station 1, including a pneumatic sample delivery system and an automatic large amount of total gamma analyzer 7. The pneumatic sample delivery system is used to transfer samples to be tested from the sample distribution platform 1 to the automatic mass total gamma analyzer 7 . The automatic mass total gamma analyzer 7 is used to obtain and analyze the gamma ray spectrum of the sample to be tested, and output the analysis results of the gamma ray spectrum, and is also used to control the delivery of the sample to be tested by the pneumatic sample delivery system.

[0028] Wherein, the automatic mass total gamma analyzer 7 includes ...

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Abstract

The invention belongs to the technical field of spent fuel aftertreatment. The invention particularly relates to an automatic mass total gamma analyzer system which is used for measuring gamma rays ofa radioactive sample to be measured in a sample distribution table and comprises an automatic mass total gamma analyzer provided with a pneumatic sample conveying system, and the pneumatic sample conveying system is used for conveying the sample to be measured from the sample distribution table to the automatic mass total gamma analyzer. And the automatic mass total gamma analyzer is used for obtaining and analyzing the gamma ray spectrum of the sample to be measured, outputting an analysis result of the gamma ray spectrum, and controlling the pneumatic sample conveying system to convey the sample. According to the system, the sample to be measured can be directly measured without pretreatment; the analysis process is simple, efficient and rapid; the sample to be measured can be recycled;the automatic acquisition of sample information, the automatic receiving and sending of a measurement bottle and the automatic measurement of the sample to be measured can be realized, finally, the unattended full-automatic analysis is realized, the labor intensity and the dosage of workers are greatly reduced, and the working efficiency is greatly improved.

Description

technical field [0001] The invention belongs to the technical field of spent fuel reprocessing, and in particular relates to an automatic mass total gamma analyzer system. Background technique [0002] Spent fuel, also known as irradiated nuclear fuel, is nuclear fuel that has been exposed to radiation and used, usually produced by nuclear reactors in nuclear power plants. Spent fuel reprocessing is the most critical link in the latter part of the nuclear fuel cycle, and is currently the most extensive treatment method for spent fuel discharged from nuclear reactors. Spent fuel reprocessing plants usually adopt the PUREX process, which utilizes the high extractability of U(VI) and Pu(IV) by tributyl phosphate (TBP) and the easy oxidation and reduction of Pu to realize U, The extraction and mutual separation of Pu mainly include uranium and plutonium decontamination cycle, uranium purification cycle and plutonium purification cycle. In the whole process, the total gamma mea...

Claims

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Application Information

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IPC IPC(8): G01T1/36G01T7/08
CPCG01T1/36G01T7/08
Inventor 邵少雄范德军束玉珍徐平郑维明
Owner CHINA INSTITUTE OF ATOMIC ENERGY
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