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Electrochemical preparation of hydrotalcite in-situ treatment method for nuclear power plant radioactive waste liquid containing strontium
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A radioactive waste liquid, in-situ treatment technology, applied in radioactive purification, nuclear engineering, etc., can solve the problems of affecting the adsorption effect of metal ions and affecting the adsorption activity, and achieve the effects of significant precipitation effect, enhanced adsorption effect, and strong adsorption activity
Active Publication Date: 2021-11-19
EAST CHINA UNIV OF SCI & TECH
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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
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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 electrochemically preparing hydrotalcite to treat radioactive waste liquid containing strontium in a nuclear power plant in situ, and the preparation contains Sr 2+ The simulated radioactive waste water is used as the electrolyte, the alkali solution and the acid solution are added dropwise, and the pH is adjusted to 5-11, and the electrolysis is performed using dual power sources. One group uses aluminum sheets as anodes, graphite as cathodes, and DC stabilized power supplies as power sources; Two zinc sheets are used as the cathode and anode respectively, and the pulse power supply is used as the power supply, and the cathode and anode are changed by inverted poles, and electrolytic synthesis is carried out under constant temperature conditions. After the reaction is completed, the electrolyte is left to stand, filtered, and solid-liquid separation is completed. Simulate the purification treatment of waste liquid. The present invention does not need to add a large amount of medicaments or adsorbents, only needs to control a certain concentration of nitrate and chloride ions in the waste liquid, without secondary pollution, and achieves efficient removal of various divalent radioactive metal ions. The present invention only describes For the removal of strontium ions and the efficient separation of solid and liquid, the required materials come from a wide range of sources, the process is simple and the operation is convenient.
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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