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Method for electrochemical preparation of hydrotalcite for in-situ treatment on strontium-containing radioactive waste liquid in power plant

A technology for in-situ treatment of radioactive waste liquid, applied in radioactive purification, nuclear engineering and other directions, can solve the problems of affecting the adsorption effect of metal ions, affecting the adsorption activity, etc., and achieve the effect of significant precipitation effect, enhanced adsorption effect, and efficient removal.

Active Publication Date: 2018-09-25
EAST CHINA UNIV OF SCI & TECH
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

This patent uses the co-precipitation method to synthesize hydrotalcite, and then puts it into the wastewater to be treated for adsorption, while the present application uses the electrochemical method to synthesize hydrotalcite in situ. One-site synthesis, no need to separate and dry after synthesis before adding, this operation will affect the adsorption activity of hydrotalcite, thus affecting its adsorption effect on metal ions

Method used

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Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0034] The volume of the simulated waste water sample is 500mL, the reaction temperature is controlled by a constant temperature water bath, and the solution is mixed by electric stirring when adding dilute acid and lye dropwise to adjust the pH.

[0035] The experimental steps are:

[0036] 1) Strontium chloride (SrCl 2 ) dubbed Sr 2+ For a solution with a concentration of 50mg / L, take 50ml and add it to a 500ml volumetric flask to configure Sr 2+ Simulated waste liquid with a concentration of about 5mg / L;

[0037] 2) Weigh boric acid (H 3 BO 3 ), electrolyte NaNO 3 , NaCl was added to the 500ml volumetric flask, so that the concentration of boric acid in the solution was 1000mg / L; so that NaNO 3 The concentration is 0.05mol / L, and the NaCl concentration is 0.1mol / L;

[0038] 3) Transfer 500ml of simulated waste liquid into a 600ml container, and add 60g / L of NaOH and 4mol / L of HNO 3 Adjust the pH value of the solution to the experimental design value;

[0039] 4) Se...

Embodiment 2

[0045] The experimental procedure is the same as in Example 1, and the process parameters adopted are different from Example 1, specifically as follows: the temperature of the constant temperature water bath is 40°C, the initial pH of the solution adjusted by acid and alkali is 9, and the current density of the aluminum electrode DC power supply is 45mA / cm 2 , the zinc electrode DC power supply current density is 135mA / cm 2 , reaction time 120min, NaNO 3 The concentration is 0.05mol / L, the NaCl concentration is 0.1mol / L, the rotation speed is 500r / min, and the distance between electrodes is 2cm.

[0046] The experimental results are: Sr 2+ The concentration is 669μg / L, the sediment color is white, and the precipitation effect is good.

Embodiment 3

[0048] The experimental procedure is the same as in Example 1, and the process parameters adopted are different from Example 1, specifically as follows: the temperature of the constant temperature water bath is 40°C, the initial pH of the solution adjusted by acid and alkali is 9, and the current density of the aluminum electrode DC power supply is 135mA / cm 2 , the zinc electrode pulse power supply current density is 135mA / cm 2 , reaction time 120min, NaNO 3 The concentration is 0.05mol / L, the NaCl concentration is 0.1mol / L, the rotation speed is 500r / min, and the distance between electrodes is 2cm.

[0049] The experimental results are: Sr 2+ The concentration is 344μg / L, the sediment color is white, and the precipitation effect is good.

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Abstract

The invention relates to a method for electrochemical preparation of hydrotalcite for in-situ treatment on a strontium-containing radioactive waste liquid in a power plant. The method comprises the following steps: preparing simulated radioactive wastewater with Sr<2+> as electrolyte, dropping an alkali solution and an acid solution, adjusting the pH value to be 5-11, and carrying out electrolysiswith double power supplies, wherein a direct-current voltage stabilizing power supply with an aluminum piece as an anode and graphite as a cathode is adopted as one group of the power supplies, and apulse power supply with two zinc pieces as an anode and a cathode respectively is adopted as the other group of the power supplies; alternating the anodes and the cathodes through inverse electrodes,carrying out electrolysis synthesis under a constant temperature condition, after the reaction is completed, leaving the electrolyte to stand, filtering, and carrying out solid-liquid separation, soas to complete simulation waste liquid purification treatment. By adopting the method, a great amount of chemicals or absorbents are not needed, only nitrate radicals and chloride ions of certain concentrations in the waste liquid need to be controlled, no secondary pollution can be caused, efficient removal of multiple divalent radioactive metallic ions can be achieved, and the method only aims at removal of strontium ions, is capable achieving efficient solid-liquid separation, is wide in material resource, simple in process and convenient to operate.

Description

technical field [0001] The invention belongs to the technical field of environmental protection, and relates to a method for treating radioactive waste liquid of a nuclear power plant, in particular to a method for in-situ treatment of radioactive waste liquid containing strontium in a nuclear power plant by electrochemically preparing hydrotalcite. Background technique [0002] In the 1950s, the development of nuclear energy turned to peaceful purposes. With the continuous development of nuclear energy technology, radioactive waste water continued to enter the environment, seriously threatening environmental safety and human health. Therefore, it is of great significance to study how to safely, economically and effectively dispose of nuclear waste. [0003] my country usually divides radioactive waste liquid into three categories according to the level of radioactivity, namely high-level radioactive waste liquid, medium-level radioactive waste liquid and low-level radioactiv...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/20G21F9/12G21F9/10
CPCG21F9/10G21F9/12G21F9/20
Inventor 黄光团邵利锋黄立姜丽瞿玲
Owner EAST CHINA UNIV OF SCI & TECH
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