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Method for analyzing plutonium in waste ion exchange resin sample

An exchange resin and analysis method technology, which is applied in the field of analysis of plutonium in waste ion exchange resin samples, can solve the problems of inability to meet the needs of nuclear facility decommissioning and three waste treatment projects, and the lack of Pu analysis methods.

Pending Publication Date: 2021-03-09
THE 404 COMPANY LIMITED CHINA NAT NUCLEAR
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  • Description
  • Claims
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Problems solved by technology

At present, no analysis method for Pu in waste resin samples has been found, which cannot meet the needs of nuclear facility decommissioning and three wastes treatment projects

Method used

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  • Method for analyzing plutonium in waste ion exchange resin sample
  • Method for analyzing plutonium in waste ion exchange resin sample
  • Method for analyzing plutonium in waste ion exchange resin sample

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Embodiment Construction

[0054] The present invention will be described in detail below in conjunction with the accompanying drawings and specific embodiments.

[0055] The present invention consists of 1) sample pretreatment; 2) separation and enrichment of Pu; 3) analysis and determination of Pu, the analysis process is shown in figure 1 .

[0056] 1) Sample pretreatment

[0057] A certain amount of waste resin sample was weighed and dissolved with nitric acid solution after high-temperature carbonization and high-pressure digestion.

[0058] 2) Pu separation and enrichment

[0059] For the waste resin solution with low radioactive level, use TEVA extraction chromatography resin to separate and purify Pu;

[0060] For the waste resin solution with moderate radioactivity level, TiOA extraction was used to separate and purify Pu.

[0061] 3) Pu determination

[0062]For the Pu eluent after TEVA separation and purification, the α source was prepared by cerium fluoride micro-deposition method, and ...

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Abstract

The invention belongs to the technical field of nuclear facility decommissioning and three-waste treatment, and particularly relates to a method for analyzing plutonium in a waste ion exchange resin sample. The method comprises the following steps of carrying out sample pretreatment: weighing a waste resin sample, carrying out high-temperature carbonization and high-pressure digestion, and dissolving with a nitric acid solution; carrying out Pu separation and enrichment: separating and purifying Pu from the waste resin dissolving solution with a low radioactivity level by adopting a TEVA extraction chromatography resin; extracting, separating and purifying Pu of the waste resin dissolving solution with a medium radioactive level by adopting TiOA; carrying out Pu determination: preparing analpha source from a Pu leacheate subjected to TEVA separation and purification by using a cerium fluoride micro-deposition method, and determining the energy of 238-240 Pu by using an alpha energy spectrum, and selecting 5.11 MeV- 5.50 MeV; and measuring Pu for the Pu extracted, separated and purified by TiOA by using a liquid scintillation counter. The method realizes analysis and determinationof Pu in the waste resin sample.

Description

technical field [0001] The invention belongs to the technical field of decommissioning of nuclear facilities and treatment of three wastes, and in particular relates to a method for analyzing plutonium in waste ion exchange resin samples. Background technique [0002] In the process of nuclear fuel cycle, isotope production and application, and radiochemical experiments, ion exchange technology is widely used for nuclide separation. Ion exchange technology has made great contributions to the development of nuclear technology in my country. In the management, removal and waste of radionuclides The processing and other aspects have an irreplaceable role. The low-level radioactive waste liquid generated during the operation and decommissioning of nuclear facilities is treated with ion exchange resin, which has a high purification factor and occupies a high position in the traditional radioactive wastewater treatment. At present, most of the process wastewater generated by react...

Claims

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Application Information

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IPC IPC(8): G01T1/36
CPCG01T1/362
Inventor 靳小军陈忠恭乔淑霞高琪李玉芳刘立姝
Owner THE 404 COMPANY LIMITED CHINA NAT NUCLEAR
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