Preparation method of liquid alpha irradiation source

Abstract

The invention relates to a preparation method of a liquid alpha irradiation source to solve the problem that an existing alpha irradiation source used for alpha radiolysis behavior research is low in dosage rate, can not meet the requirement for immediate measurement and can not reflect the true radiolysis condition of a measured object. The preparation method of the liquid alpha irradiation source includes a first step of conducting electrochemistry dissolution, namely, utilizing an electrolytic cell which is divided into a cathode chamber and an anode chamber through a partition film, and utilizing silver nitrate to conduct catalyzing, a second step of purifying, namely, removing silver through an anion exchange method, and a third step of calibrating the dosage rate. The liquid alpha irradiation source prepared through the preparation method of the liquid alpha irradiation source is high in dosage rate and capable of meeting the requirement of the alpha radiolysis behavior research of chemical reagents for immediacy of measurement in a post processing procedure, and reflects the radiolysis condition of the measured object in a relatively real mode. The liquid alpha irradiation source can also be suitable for the radiolysis research on other reagents in an aqueous phase and on various organic solvents.

Description

technical field [0001] The invention relates to a preparation method of a radiation source, in particular to a preparation method of a liquid alpha radiation source. Background technique [0002] The objects of spent fuel reprocessing are mainly spent fuel discharged from nuclear power plant reactors. The biggest feature of spent fuel is that it is extremely radioactive. When the spent fuel is unloaded from the reactor, no matter whether it reaches the designed burnup depth or not, it always contains a certain amount of unfissioned nuclides and newly generated nuclides. When spent fuel is reprocessed, the radioactivity in the reprocessing process comes from 235 U 238 U 239 Pu, 237 Np, 241 Am, and long-lived, high-yield splinter elements from nuclear fission, such as 95 Zr, 95 Nb( 95 Decay daughters of Zr), ruthenium ( 103 Ru, 106 Ru), some alkali metals (such as 137 Cs), alkaline earth metals (such as 90 Sr) and rare earth elements (such as 144 Ce, 147 Pm) etc...

AI Technical Summary

Problems solved by technology

[0005] In order to solve the problems that the existing α radiation source used for the study of α radiolysis behavior has a low dose rate, cannot meet the requirements of real-time measurement, and cannot reflect the real radiolysis status of the measured object, the invention provides a liquid α radiation source The preparation method, this method comprises the following steps: