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CN109987738A - A kind of uranium recovery process from uranium-containing waste liquid - Google Patents

A kind of uranium recovery process from uranium-containing waste liquid Download PDF

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CN109987738A
CN109987738A CN201711477628.0A CN201711477628A CN109987738A CN 109987738 A CN109987738 A CN 109987738A CN 201711477628 A CN201711477628 A CN 201711477628A CN 109987738 A CN109987738 A CN 109987738A
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uranium
waste liquid
filtration
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concentration
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李天福
李贺成
马治军
顾跃雷
耿龙
陈建勇
邹琛华
李英锋
饶申直
周天华
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NUCLEAR INDUSTRY NO 8 INSTITUTE
404 Co Ltd China National Nuclear Corp
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02FTREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F9/00Multistage treatment of water, waste water or sewage
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    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B60/00Obtaining metals of atomic number 87 or higher, i.e. radioactive metals
    • C22B60/02Obtaining thorium, uranium, or other actinides
    • C22B60/0204Obtaining thorium, uranium, or other actinides obtaining uranium
    • C22B60/0217Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes
    • C22B60/0252Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries
    • C22B60/0265Obtaining thorium, uranium, or other actinides obtaining uranium by wet processes treatment or purification of solutions or of liquors or of slurries extraction by solid resins
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    • C22METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22BPRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B7/00Working up raw materials other than ores, e.g. scrap, to produce non-ferrous metals and compounds thereof; Methods of a general interest or applied to the winning of more than two metals
    • C22B7/005Separation by a physical processing technique only, e.g. by mechanical breaking
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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    • C02F1/00Treatment of water, waste water, or sewage
    • C02F1/28Treatment of water, waste water, or sewage by sorption
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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    • C02F1/00Treatment of water, waste water, or sewage
    • C02F1/44Treatment of water, waste water, or sewage by dialysis, osmosis or reverse osmosis
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02FTREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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    • C02TREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02FTREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
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    • C02FTREATMENT OF WATER, WASTE WATER, SEWAGE, OR SLUDGE
    • C02F2301/00General aspects of water treatment
    • C02F2301/08Multistage treatments, e.g. repetition of the same process step under different conditions
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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Abstract

本发明属于一种含铀废液中铀回收工艺。(1)调节含铀废水PH值;(2)废液过滤;(3)废液吸附,铀浓度≥200mg/L后送至新型吸附材料系统,2次过滤产生的清液和3次过滤系统产生的浓液返回送至预过滤中间储罐中,继续通过1次过滤系统进行浓缩处理,3次过滤系统产生的清液铀浓度为0.02‑0.03mg/L,送至排放罐进行排放,3次过滤系统产生的浓液,铀浓度为200mg/L,采用新型铀吸附材料吸附;(4)饱和后进行解析,最终产生铀浓度约为1‑5g/L以上的含铀物料。本发明的优点是,膜处理技术设备简单可实现自动控制,常温操作、无化学变化、能耗低、清洁无污染。实现连锁控制对膜处理系统进行安全保护。The invention belongs to a uranium recovery process in uranium-containing waste liquid. (1) Adjust the pH value of uranium-containing wastewater; (2) Filtration of waste liquid; (3) Adsorption of waste liquid, uranium concentration ≥ 200 mg/L and then sent to the new adsorption material system, the clear liquid produced by the 2nd filtration and the 3rd filtration system The produced concentrated solution is sent back to the pre-filtration intermediate storage tank, and continues to be concentrated through the 1st filtration system. The concentration of uranium in the clear liquid produced by the 3rd filtration system is 0.02-0.03mg/L, and sent to the discharge tank for discharge, 3 The concentrate produced by the secondary filtration system has a uranium concentration of 200mg/L, which is adsorbed by a new type of uranium adsorption material; (4) After saturation, analysis is carried out, and finally a uranium-containing material with a uranium concentration of about 1-5g/L or more is produced. The advantages of the present invention are that the membrane treatment technology equipment is simple and can realize automatic control, normal temperature operation, no chemical change, low energy consumption, clean and pollution-free. Realize interlocking control to protect the membrane processing system safely.

Description

一种含铀废液中铀回收工艺A kind of uranium recovery process from uranium-containing waste liquid

技术领域technical field

本发明属于一种含铀废水中铀回收净化工艺,具体涉及一种含铀废液中 铀回收工艺。The invention belongs to a uranium recovery and purification process in uranium-containing waste water, in particular to a uranium recovery process in uranium-containing waste water.

背景技术Background technique

在天然六氟化铀生产过程中,会产生大量的含铀工艺废液。金属铀资源 的回收利用及废水达标排放问题都是行业范围内广泛关注的。In the production process of natural uranium hexafluoride, a large amount of uranium-containing process waste liquid will be produced. The recycling and utilization of metallic uranium resources and the discharge of wastewater up to the standard are widely concerned in the industry.

铀转化生产过程中产生的含铀废水中,尤其是氟化尾气淋洗工序产生的 碱性含铀废液体系复杂。目前采用的离子交换技术选取的国产树脂进行除铀, 难以实现<50μg/L达标排放指标,且会产生大量的废树脂难以处理。而通过 调研,国内外工业用吸附材料(如:新型树脂、新型合成纤维)可实现废水 达标排放,但该种材料价格昂贵,会增加废水处理设施的运行成本。因此本 设计采用膜处理系统使处理大部分废水实现达标排放,而膜处理产生的少量 浓缩液采用结合新型吸附材料进行处理的方式,一方面减少吸附材料的使用 量,另一方面,解决膜处理浓缩液无法达标排放的问题。Among the uranium-containing wastewater produced in the uranium conversion production process, especially the alkaline uranium-containing wastewater generated in the fluorination tail gas leaching process, the system is complex. The domestic resin selected by the currently used ion exchange technology for uranium removal is difficult to achieve the discharge target of <50μg/L, and a large amount of waste resin is generated which is difficult to handle. Through research, industrial adsorption materials at home and abroad (such as new resins, new synthetic fibers) can achieve wastewater discharge standards, but such materials are expensive and will increase the operating cost of wastewater treatment facilities. Therefore, the membrane treatment system is used in this design to achieve discharge of most of the wastewater, and a small amount of concentrated liquid produced by membrane treatment is treated with new adsorption materials. On the one hand, the use of adsorbent materials is reduced. The problem that the concentrate cannot meet the discharge standard.

国内外膜处理技术及离子交换技术均有用于含铀废水处理的成功经验, 本发明专利主要针对国内铀转化生产线含铀废水处理的流程化设计,实现全 流程可最优化控制。Both domestic and foreign membrane treatment technology and ion exchange technology have successful experience in the treatment of uranium-containing wastewater. The patent of this invention is mainly aimed at the process design of uranium-containing wastewater treatment in domestic uranium conversion production lines, and the entire process can be optimally controlled.

发明内容SUMMARY OF THE INVENTION

本发明的目的是提供一种含铀废液中铀回收工艺,选取了膜处理系统及 新型吸附材料作为含铀废水处理工艺的单元,实现含铀废水处理后铀浓度< 50μg/L的目的。The purpose of the present invention is to provide a uranium recovery process in a uranium-containing waste liquid, and a membrane treatment system and a novel adsorption material are selected as the units of the uranium-containing wastewater treatment process, so as to achieve the purpose of uranium concentration < 50 μg/L after the uranium-containing wastewater treatment.

本发明是这样实现的,一种含铀废液中铀回收工艺,它包括如下步骤,The present invention is achieved in this way, a uranium recovery process in a uranium-containing waste liquid, which comprises the following steps:

(1)调节含铀废水PH值;(1) Adjust the pH value of uranium-containing wastewater;

(2)废液过滤;(2) Waste liquid filtration;

(3)废液吸附,铀浓度≥200mg/L后送至新型吸附材料系统,2次过滤 产生的清液和3次过滤系统产生的浓液返回送至预过滤中间储罐中,继续通 过1次过滤系统进行浓缩处理,3次过滤系统产生的清液铀浓度为 0.02-0.03mg/L,送至排放罐进行排放,3次过滤系统产生的浓液,铀浓度为 200mg/L,采用新型铀吸附材料吸附;(3) Waste liquid adsorption, the uranium concentration ≥ 200mg/L is sent to the new adsorption material system, the clear liquid produced by the 2nd filtration and the concentrate produced by the 3rd filtration system are returned to the pre-filtration intermediate storage tank, and continue to pass through 1 The secondary filtration system is concentrated. The uranium concentration of the clear liquid produced by the 3rd filtration system is 0.02-0.03mg/L, which is sent to the discharge tank for discharge. The concentrate produced by the 3rd filtration system has a uranium concentration of 200mg/L. Uranium adsorption material adsorption;

(4)饱和后进行解析,最终产生铀浓度约为1-5g/L以上的含铀物料。(4) Perform analysis after saturation, and finally produce uranium-containing materials with a uranium concentration of about 1-5 g/L or more.

所述的步骤(1)含铀废水先进行PH调节,PH调节至小于3。In the step (1), the uranium-containing wastewater is first adjusted to pH, and the pH is adjusted to less than 3.

所述的步骤(2)将调配好的废液送至1次纳滤过滤系统,1次过滤系统 产生的浓液送至2次过滤系统继续进行浓缩,清液送至3次纳滤过滤系统继 续进行浓缩;2次过滤系统产生的浓液需进行循环处理。In the step (2), the prepared waste liquid is sent to the 1st nanofiltration system, the concentrated liquid produced by the 1st filtration system is sent to the 2nd filtration system to continue to concentrate, and the clear liquid is sent to the 3rd nanofiltration system. Continue to concentrate; the concentrate produced by the secondary filtration system needs to be recycled.

所述的步骤(2)所述的1次纳滤过滤系统,泵工作温度<40℃,泵压力 小于2.0Mpa。In the 1st nanofiltration filtration system described in the step (2), the working temperature of the pump is less than 40°C, and the pressure of the pump is less than 2.0Mpa.

所述的步骤(2)所述的2次纳滤过滤系统,泵工作温度<40℃,泵压力 小于2.0Mpa。In the secondary nanofiltration filtration system described in the step (2), the working temperature of the pump is less than 40°C, and the pressure of the pump is less than 2.0Mpa.

所述的步骤(2)所述的2次纳滤过滤系统,泵工作温度<50℃,泵压力 小于2.0Mpa。In the secondary nanofiltration filtration system of the step (2), the working temperature of the pump is less than 50°C, and the pressure of the pump is less than 2.0Mpa.

本发明的优点是,膜处理技术设备简单可实现自动控制,常温操作、无 化学变化、能耗低、清洁无污染。实现连锁控制对膜处理系统进行安全保护。The advantages of the present invention are that the membrane treatment technology equipment is simple and can realize automatic control, normal temperature operation, no chemical change, low energy consumption, clean and pollution-free. Realize interlocking control to protect the membrane processing system safely.

具体实施方式Detailed ways

下面结合具体实施例对本发明进行详细介绍:The present invention is described in detail below in conjunction with specific embodiments:

一种含铀废液中铀回收工艺,它包括如下步骤:A uranium recovery process in a uranium-containing waste liquid, which comprises the following steps:

(1)调节含铀废水PH值,含铀废水先进行PH调节,PH调节至小于3;(1) Adjust the pH value of the uranium-containing wastewater, first adjust the pH of the uranium-containing wastewater, and adjust the pH to less than 3;

(2)废液过滤,将调配好的废液送至1次纳滤过滤系统(泵工作温度< 40℃,泵压力小于2.0Mpa),1次过滤系统产生的浓液(铀浓度约20-50mg/L) 送至2次过滤系统(泵工作温度<40℃,泵压力小于2.0Mpa)继续进行浓缩, 清液(铀浓度<10mg/L)送至3次纳滤过滤系统(泵工作温度<50℃,泵压力 小于2.0Mpa)继续进行浓缩;2次过滤系统产生的浓液需进行循环处理;(2) Filtration of waste liquid, the prepared waste liquid is sent to the primary nanofiltration filtration system (the working temperature of the pump is less than 40°C, and the pump pressure is less than 2.0Mpa), and the concentrated solution produced by the primary filtration system (the uranium concentration is about 20- 50mg/L) to the 2nd filtration system (pump working temperature <40℃, pump pressure less than 2.0Mpa) to continue enrichment, the clear liquid (uranium concentration <10mg/L) is sent to the 3rd nanofiltration filtration system (pump working temperature <50°C, pump pressure less than 2.0Mpa) to continue to concentrate; the concentrate produced by the secondary filtration system needs to be recycled;

(3)废液吸附,铀浓度≥200mg/L后送至新型吸附材料系统,2次过滤 产生的清液和3次过滤系统产生的浓液返回送至预过滤中间储罐中,继续通 过1次过滤系统进行浓缩处理,3次过滤系统产生的清液铀浓度约为 0.02-0.03mg/L,送至排放罐进行排放,3次过滤系统产生的浓液,铀浓度为 200mg/L,采用新型铀吸附材料吸附;(3) Waste liquid adsorption, the uranium concentration ≥ 200mg/L is sent to the new adsorption material system, the clear liquid produced by the 2nd filtration and the concentrate produced by the 3rd filtration system are returned to the pre-filtration intermediate storage tank, and continue to pass through 1 The secondary filtration system is concentrated. The uranium concentration of the clear liquid produced by the 3rd filtration system is about 0.02-0.03mg/L, which is sent to the discharge tank for discharge. The concentrate produced by the 3rd filtration system has a uranium concentration of 200mg/L. Adsorption of new uranium adsorption materials;

(4)饱和后进行解析,最终产生铀浓度约为1-5g/L以上的含铀物料。(4) Perform analysis after saturation, and finally produce uranium-containing materials with a uranium concentration of about 1-5 g/L or more.

按照该技术方案可实现含铀废水的连续处理,3次过滤产生的清液的流 量视为该系统的处理能力。通过膜系统选型对1次、2次过滤进行设计以实 现全系统连续循环运行。另外,该系统中膜单元、管道、泵、阀门、容器均 使用耐酸材质,同时为了保护系统需对各供料罐设置连锁停泵设计。According to this technical scheme, continuous treatment of uranium-containing wastewater can be realized, and the flow of clear liquid produced by 3 times of filtration is regarded as the treatment capacity of the system. The 1st and 2nd filtration are designed through the membrane system selection to realize the continuous cycle operation of the whole system. In addition, the membrane units, pipes, pumps, valves and containers in the system are made of acid-resistant materials, and at the same time, in order to protect the system, an interlocking pump stop design is required for each feeding tank.

预处理主要指机械过滤,是为了除去原液中的悬浮物、胶体、浊度、色 度、异味等淤泥、大颗粒杂质、粘土和极少量的胶体等物质,防止这些物质 对后期超滤,纳滤,反渗透膜的影响。主要过滤方式有盘式过滤,袋式过滤。 处理系统膜的材质为聚丙烯的材质,耐酸碱性较强。Pretreatment mainly refers to mechanical filtration, which is to remove suspended solids, colloids, turbidity, chromaticity, odor and other substances in the raw solution, large particles of impurities, clay and a very small amount of colloids and other substances, to prevent these substances from affecting the ultrafiltration in the later stage. Filtration, reverse osmosis membrane effect. The main filtration methods are disc filtration and bag filtration. The material of the treatment system membrane is polypropylene, which has strong acid and alkali resistance.

微滤是利用微孔径的大小,在压差为推动力下,将溶液中大于膜孔径的 微粒等悬浮物质截留下来,达到微粒的去除与溶液澄清的膜分离技术。本发 明所用的微孔膜孔径为1μm(微滤内所使用的是滤芯,根据滤芯的不同可以 分离出不同范围内的大颗粒悬浮物),适宜pH值范围为0-14,温度在(5~ 50)℃,能截留粘土、悬浮物等物质,能够对后续的超滤,纳滤以及反渗透 的膜起到保护作用。由于微滤所去除的粒子通常远大于反渗透和超滤分离的 溶质及大分子,故没有渗透压,操作压差较小,约为(0.01~0.2)MPa。Microfiltration is a membrane separation technology that uses the size of the pore size and the pressure difference as the driving force to intercept suspended substances such as particles in the solution that are larger than the pore size of the membrane, so as to achieve the removal of particles and the clarification of the solution. The pore size of the microporous membrane used in the present invention is 1 μm (the filter element is used in the microfiltration, and the large particle suspended matter in different ranges can be separated according to the difference of the filter element), the suitable pH value range is 0-14, and the temperature is (5 ~ 50) ℃, can retain clay, suspended solids and other substances, can play a protective role in the subsequent ultrafiltration, nanofiltration and reverse osmosis membranes. Since the particles removed by microfiltration are usually much larger than the solutes and macromolecules separated by reverse osmosis and ultrafiltration, there is no osmotic pressure, and the operating pressure difference is small, about (0.01-0.2) MPa.

纳滤膜是介于反渗透和超滤膜之间的一种压力驱动膜,是近年来国际上 发展较快的膜品牌之一。截留分子量不同的纳滤膜,其所过滤的离子等物质 存在一定的差异。溶液通过纳滤膜时,在压力的作用下,能够透过纳滤膜的 物质从透过液中分离,未能透过的部分被截留。Nanofiltration membrane is a pressure-driven membrane between reverse osmosis and ultrafiltration membrane, and it is one of the fastest developing membrane brands in the world in recent years. Nanofiltration membranes with different molecular weight cut-offs have certain differences in the ions and other substances they filter. When the solution passes through the nanofiltration membrane, under the action of pressure, the substances that can pass through the nanofiltration membrane are separated from the permeate, and the part that cannot pass through is retained.

本发明所采用纳滤膜的材料为聚酰胺复合膜,他们的截留分子量分别为 300道尔顿(一次纳滤膜)、200道尔顿(二次纳滤膜)和200道尔顿(三次 纳滤膜)。纳滤膜适宜操作温度在(5~45)℃工作压力根据膜过滤面积、处 理能力等进行泵的压力选择,连续运行pH值范围为2~11。The materials of the nanofiltration membranes used in the present invention are polyamide composite membranes, and their molecular weight cutoffs are 300 Daltons (primary nanofiltration membranes), 200 Daltons (secondary nanofiltration membranes) and 200 Daltons (tertiary nanofiltration membranes), respectively. Nanofiltration). The suitable operating temperature of nanofiltration membrane is (5~45)℃. The working pressure is selected according to the membrane filtration area and processing capacity. The pH value range of continuous operation is 2~11.

Claims (6)

1. uranium recovery process in a kind of uranium-bearing waste liquid, it is characterised in that: it includes the following steps,
(1) uranium-containing waste water pH value is adjusted;
(2) waste liquid filters;
(3) waste liquid adsorbs, and the clear liquid generated to novel absorption material system, 2 filterings and 3 times are sent after uranium concentration >=200mg/L The dope that filtration system generates is returned and is recycled in pre-filtering intermediate storage tank, is continued through 1 filtration system and is carried out concentration, and 3 The clear liquid uranium concentration that secondary filtration system generates is 0.02-0.03mg/L, send to blowdown vessel and is discharged, and 3 times filtration system generates Dope, uranium concentration 200mg/L, using Novel Uranium adsorbent material adsorb;
(4) it is parsed after being saturated, it is final to generate the uranium-containing materials that uranium concentration is about 1-5g/L or more.
2. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: described step (1) uranium-bearing Waste water first carries out PH adjusting, and PH is adjusted to less than 3.
3. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) will be adjusted The waste liquid prepared is sent to 1 nanofiltration filtration system, the dope that 1 filtration system generates send to 2 filtration systems continue it is dense Contracting, clear liquid, which is sent to 3 nanofiltration filtration systems, to be continued to be concentrated;The dope that 2 filtration systems generate need to carry out circular treatment.
4. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described 1 nanofiltration filtration system, 40 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
5. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described 2 nanofiltration filtration systems, 40 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
6. uranium recovery process in a kind of uranium-bearing waste liquid as described in claim 1, it is characterised in that: the step (2) is described 2 nanofiltration filtration systems, 50 DEG C of pump work temperature <, pump pressure be less than 2.0Mpa.
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