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Measurement method of denitrification rate during calcination of radioactive waste liquid

A radioactive waste liquid and measurement method technology, applied in the field of radioactive waste liquid treatment process, can solve the problems of limited electrode life, limited large-scale application, high energy consumption, etc.

Active Publication Date: 2022-08-09
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

Electrochemical denitrification is easy to control, safe, and does not require the addition of other reagents, but high energy consumption and limited electrode life limit its large-scale application

Method used

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  • Measurement method of denitrification rate during calcination of radioactive waste liquid
  • Measurement method of denitrification rate during calcination of radioactive waste liquid
  • Measurement method of denitrification rate during calcination of radioactive waste liquid

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Embodiment Construction

[0014] In order to make the objectives, technical solutions and advantages of the present application clearer, the technical solutions of the present application will be described clearly and completely below with reference to the accompanying drawings of the embodiments of the present application. Obviously, the described embodiment is one embodiment of the present application, but not all embodiments. Based on the described embodiments of the present application, all other embodiments obtained by those of ordinary skill in the art without creative work fall within the protection scope of the present application.

[0015] It should be noted that, unless otherwise defined, the technical or scientific terms used in the present application shall have the usual meanings understood by those with ordinary skills in the field to which the present application belongs. If descriptions such as "first" and "second" are involved in the whole text, the descriptions such as "first" and "se...

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Abstract

A method for measuring the denitrification rate during the calcination of radioactive waste liquid, comprising the following steps: measuring the nitrate content N in the radioactive waste liquid 1 ; measure the nitrate content N in the calcined product obtained after the radioactive waste liquid is calcined 2 ; according to the nitrate content N 1 and the nitrate content N 2 , calculate the denitrification rate. The method for measuring the denitration rate in the above-mentioned radioactive waste liquid calcination process, by determining the amount of nitrate in the generated calcined product, using material conservation to calculate the amount of nitrate lost, and then calculating the denitrification rate, the accurate calculation of the denitration rate is realized, It provides a reliable reference or basis for the evaluation of the denitration effect and the determination of the ratio of the calcined product to the glass base material.

Description

technical field [0001] The embodiments of the present application relate to the technical field of radioactive waste liquid treatment technology, and in particular to a method for measuring the denitration rate during the calcination of radioactive waste liquid. Background technique [0002] The radioactive waste liquid produced by the reprocessing of spent fuel has the characteristics of high specific activity, high heat release rate, long half-life containing nuclides and complex chemical composition. How to safely and effectively treat the radioactive waste liquid is an important factor affecting the sustainable development of the nuclear industry one. In recent years, the vitrification process has been used to treat radioactive waste liquids. In the vitrification process, the radioactive waste liquid is pretreated by calcination to convert it into oxides (called calcination products), and then it is mixed with the glass substrate in a certain proportion in a furnace, me...

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): G01N33/00G01N30/96G01N23/223
CPCG01N33/00G01N30/96G01N23/223Y02E30/30
Inventor 贺诚张华洪业李玉松张克乾汪润慈李宝军李扬郄东生朱冬冬谭盛恒常煚鲜亮
Owner CHINA INSTITUTE OF ATOMIC ENERGY