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Method for recycling metal generated by nuclear fuel analysis from waste graphite crucible

A graphite crucible and nuclear fuel technology, applied in the field of solid analysis waste treatment, can solve the problems of poor effect, low recovery efficiency of uranium and plutonium, incomplete transfer of uranium and plutonium, etc., and achieve the effect of efficient recovery

Inactive Publication Date: 2018-12-07
MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0004] However, graphite is a porous substance, and under the action of concentrated acid, the surface of graphite will be oxidized and grafted with functional groups that have a strong interaction with metal ions, resulting in the resorption of uranium and plutonium in the liquid phase by the graphite matrix, so this method is used Recovery of uranium and plutonium is poor and graphite must be further processed
[0005] The problem of incomplete transfer of uranium and plutonium in the above technical centers not only leads to low recovery efficiency of uranium and plutonium, but also requires further processing of graphite crucibles

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0027] (1) Put an unused graphite crucible without metal and molybdenum trioxide in a ball mill pot at a weight ratio of 1:4, and use a planetary ball mill to grind for 5 hours at a revolution speed of 300 rpm to obtain a mesh size greater than 100 mesh powder;

[0028] (2) Take 1 g of the obtained powder and put it into a tube furnace, and heat it at a flow rate of 100 ml / min in argon at 10 o C / min heating rate up to 900 o C, maintain the temperature for 2 hours, turn off the gas, and obtain powder after natural cooling;

[0029] (3) Add 20 milliliters of the obtained powder into an aqueous hydrogen peroxide solution with a mass fraction of 30 wt%, and the graphite will vaporize rapidly to obtain a clear and transparent liquid. After 1 hour, it is measured that there is no organic carbon in the liquid, and the vaporization rate of graphite is 100%;

[0030] (4) Add 20 milliliters of concentrated nitric acid to the obtained liquid, 90 o C constant temperature 24 hours, obt...

Embodiment 2

[0040] (1) Put an unused graphite crucible without metal and molybdenum trioxide in a ball mill jar at a weight ratio of 1:10, and use a planetary ball mill to grind for 5 hours at a revolution speed of 300 rpm to obtain a mesh size greater than 100 mesh powder;

[0041] (2) Take 1 g of the obtained powder and put it into a tube furnace, and heat it at a flow rate of 100 ml / min in argon at 10 o C / min heating rate up to 900 o C, maintain the temperature for 2 hours, turn off the gas, and obtain powder after natural cooling;

[0042] (3) Add 20 milliliters of the obtained powder into an aqueous hydrogen peroxide solution with a mass fraction of 30 wt%, and the graphite will vaporize rapidly to obtain a clear and transparent liquid. After 1 hour, it is measured that there is no organic carbon in the liquid, and the vaporization rate of graphite is 100%.

Embodiment 3

[0044] (1) Put an unused graphite crucible without metal and molybdenum trioxide in a ball mill pot at a weight ratio of 1:1, and use a planetary ball mill to grind at a revolution speed of 300 rpm for 5 hours to obtain a mesh size greater than 100 mesh powder;

[0045] (2) Take 1 g of the obtained powder and put it into a tube furnace, and heat it at a flow rate of 100 ml / min in argon at 10 o C / min heating rate up to 900 o C, maintain the temperature for 6 hours, close the gas, and obtain powder after natural cooling;

[0046] (3) Add the obtained powder into 20 ml of aqueous hydrogen peroxide solution with a mass fraction of 30 wt%, gasify the graphite, filter, analyze the carbon content in the filter residue, and determine that the gasification rate of the graphite is 67%.

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Abstract

The invention provides a method for recycling metal generated by nuclear fuel analysis from a waste graphite crucible. The scheme adopts a molybdenum trioxide as a hard template for cutting graphite into lattice carbon with high chemical activity, so that the lattice carbon is oxidized into COX by hydrogen peroxide at a normal temperature; and meanwhile, molybdenum trioxide reacts with hydrogen peroxide to generate water-soluble molybdic acid peroxide, so that metal substances on graphite are completely released to enter a liquid phase, and therefore, the effect of efficiently recycling metalsubstances on the waste graphite crucible can be achieved.

Description

technical field [0001] The invention relates to the technical field of solid analysis waste treatment, and is particularly suitable for recovering valuable metals from discarded graphite crucibles after nuclear fuel analysis and detection. Background technique [0002] Nuclear fuel is the core of the reactor and plays a vital role in the safe operation of the reactor. The technical requirements for producing nuclear fuel are high, and there is a complete set of quality inspection system in the process to ensure the production of nuclear fuel that meets the requirements. Nitrogen and oxygen content is one of the key indicators of nuclear fuel quality control. [0003] At present, the reduction melting method is used to analyze the nitrogen and oxygen content in nuclear fuel, that is, the sample is placed in a graphite crucible, and the sample is melted in an inert gas by pulse heating in the presence of a flux, and the nitrogen and oxygen in the sample are respectively Conv...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C22B7/00C22B60/00
CPCC22B7/007C22B60/00Y02P10/20
Inventor 庞敏桑培伦曾甯张灏王永鹏
Owner MATERIAL INST OF CHINA ACADEMY OF ENG PHYSICS