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Method for improving technetium-washing effect in post-treatment extraction separation process

A process and extraction technology, which is applied in the field of improving the effect of technetium washing in the post-processing extraction and separation process, and achieves the effects of reducing the amount of use, reducing the content of technetium, and achieving significant economic benefits.

Active Publication Date: 2013-12-04
CHINA INSTITUTE OF ATOMIC ENERGY
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] Technetium washing process TcSS in French UP3, UP2-800 and Japan's Liusuo reprocessing plant 1 Choose 10mol / L tritiated HNO 3 solution, TcSS 2 Choose 1.5mol / L fresh HNO 3 solution, its flow conditions are commercial secrets, and have not been reported in the literature so far

Method used

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  • Method for improving technetium-washing effect in post-treatment extraction separation process
  • Method for improving technetium-washing effect in post-treatment extraction separation process

Examples

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Effect test

Embodiment 1

[0020] Such as figure 2 The conceptual flow of milling Technetium process shown, when using 8-stage mixing and settling tank, 1AP is fed from the 1st stage, TcSS 1 The concentration of nitric acid is 9mol / L, entering from the 4th stage, TcSS 2 The concentration of nitric acid is 2mol / L, entering from the 8th stage, the flow condition is 1AP:TcSS1:TcSS2=1:0.10:0.20. The experimental result shows that the decontamination coefficient of uranium to technetium is 10.9. The total amount of nitric acid used was 3.44 times the uranium content in 1AP.

Embodiment 2

[0022] When using 8-stage mixing and settling tank, 1AP is fed from the 1st stage, TcSS 1 The concentration of nitric acid is 9mol / L, entering from the 4th stage, TcSS 2 The concentration of nitric acid is 2mol / L, entering from the 8th stage, the flow condition is 1AP:TcSS1:TcSS2=1:0.15:0.245. The experimental result shows that the decontamination coefficient of uranium to technetium is 30.1. The total amount of nitric acid used was 4.87 times the uranium content in 1AP.

Embodiment 3

[0024] When using 8-stage mixing and settling tank, 1AP is fed from the 1st stage, TcSS 1 The concentration of nitric acid is 9mol / L, entering from the 4th stage, TcSS 2 The concentration of nitric acid is 2mol / L, entering from the 8th stage, the flow condition is 1AP: TcSS1: TcSS2 = 1: 0.20: 0.245. The experimental result shows that the decontamination coefficient of uranium to technetium is 55.9. The total amount of nitric acid used was 6.05 times the uranium content in 1AP.

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Abstract

The invention discloses a method for improving the technetium-washing effect in a post-treatment extraction separation process. According to the invention, 1AP adopts an acid washing process, and washing nitric acid separating total dose is improved, wherein a total nitric acid dose is 3.4-8 times (by molar ratio) that of uranium in 1AP. With the technetium-washing method provided by the invention, technetium-removing effect of the post-treatment extraction separation process is greatly improved.

Description

technical field [0001] The invention relates to the technical field of nuclear fuel reprocessing, in particular to a method for improving technetium washing effect in a posttreatment extraction and separation process. Background technique [0002] Technetium in spent fuel 235 U and 239 The fission reaction of Pu generates, where 235 U thermal neutron fission generation 99 The yield of Tc is 6.16%. In power reactor fuel, 235 When the U enrichment degree is 3.2%, and the burnup is 33000MWd / tU, each ton of spent fuel contains about 850g of technetium. As the burn-up of fuel elements deepens, the 235 As the concentration of U increases, the production of technetium also increases. Therefore, technetium is an abundant element in spent fuel, and its behavior and influence in the spent fuel reprocessing process cannot be ignored. [0003] In the uranium-plutonium co-decontamination process section (1A) of the spent fuel reprocessing Purex process, the co-extraction behavior...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C19/46C22B60/02C22B60/04C22B61/00
CPCY02E30/30Y02W30/50
Inventor 张春龙何辉唐洪彬陈延鑫
Owner CHINA INSTITUTE OF ATOMIC ENERGY