CN113526558B - A kind of method for preparing uranium nitrate by catalytic hydrogenation reduction of uranyl nitrate - Google Patents
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- 229910002007 uranyl nitrate Inorganic materials 0.000 title claims abstract description 52
- 238000000034 method Methods 0.000 title claims abstract description 39
- 238000009903 catalytic hydrogenation reaction Methods 0.000 title claims abstract description 19
- KUKDDTFBSTXDTC-UHFFFAOYSA-N uranium;hexanitrate Chemical compound [U].[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O.[O-][N+]([O-])=O KUKDDTFBSTXDTC-UHFFFAOYSA-N 0.000 title claims abstract description 9
- 230000009467 reduction Effects 0.000 title abstract description 5
- 239000007788 liquid Substances 0.000 claims abstract description 69
- 229910052770 Uranium Inorganic materials 0.000 claims abstract description 52
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 claims abstract description 52
- UFHFLCQGNIYNRP-UHFFFAOYSA-N Hydrogen Chemical compound [H][H] UFHFLCQGNIYNRP-UHFFFAOYSA-N 0.000 claims abstract description 42
- 239000001257 hydrogen Substances 0.000 claims abstract description 41
- 229910052739 hydrogen Inorganic materials 0.000 claims abstract description 41
- 238000003860 storage Methods 0.000 claims abstract description 32
- 230000008569 process Effects 0.000 claims abstract description 31
- OAKJQQAXSVQMHS-UHFFFAOYSA-N Hydrazine Chemical compound NN OAKJQQAXSVQMHS-UHFFFAOYSA-N 0.000 claims abstract description 26
- RAESLDWEUUSRLO-UHFFFAOYSA-O aminoazanium;nitrate Chemical compound [NH3+]N.[O-][N+]([O-])=O RAESLDWEUUSRLO-UHFFFAOYSA-O 0.000 claims abstract description 26
- 239000007789 gas Substances 0.000 claims abstract description 25
- 239000007791 liquid phase Substances 0.000 claims abstract description 15
- 238000000926 separation method Methods 0.000 claims abstract description 14
- 239000000203 mixture Substances 0.000 claims abstract description 13
- 239000012071 phase Substances 0.000 claims abstract description 11
- IJGRMHOSHXDMSA-UHFFFAOYSA-N Atomic nitrogen Chemical compound N#N IJGRMHOSHXDMSA-UHFFFAOYSA-N 0.000 claims abstract description 10
- 239000003513 alkali Substances 0.000 claims abstract description 9
- 229910052757 nitrogen Inorganic materials 0.000 claims abstract description 5
- 238000006243 chemical reaction Methods 0.000 claims description 60
- HEMHJVSKTPXQMS-UHFFFAOYSA-M Sodium hydroxide Chemical compound [OH-].[Na+] HEMHJVSKTPXQMS-UHFFFAOYSA-M 0.000 claims description 20
- 239000003054 catalyst Substances 0.000 claims description 15
- 238000010521 absorption reaction Methods 0.000 claims description 14
- 239000002994 raw material Substances 0.000 claims description 14
- GRYLNZFGIOXLOG-UHFFFAOYSA-N Nitric acid Chemical compound O[N+]([O-])=O GRYLNZFGIOXLOG-UHFFFAOYSA-N 0.000 claims description 12
- 229910017604 nitric acid Inorganic materials 0.000 claims description 12
- 230000009471 action Effects 0.000 claims description 7
- 229910000510 noble metal Inorganic materials 0.000 claims description 7
- 239000000243 solution Substances 0.000 claims description 7
- 150000002431 hydrogen Chemical class 0.000 claims description 5
- 238000011068 loading method Methods 0.000 claims description 5
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 4
- 229910010413 TiO 2 Inorganic materials 0.000 claims description 3
- 239000011259 mixed solution Substances 0.000 claims description 3
- 239000002912 waste gas Substances 0.000 claims description 3
- 229910052741 iridium Inorganic materials 0.000 claims description 2
- 229910052697 platinum Inorganic materials 0.000 claims description 2
- 229910052707 ruthenium Inorganic materials 0.000 claims description 2
- 239000002002 slurry Substances 0.000 claims description 2
- 238000006073 displacement reaction Methods 0.000 claims 4
- 239000007921 spray Substances 0.000 claims 2
- 239000012670 alkaline solution Substances 0.000 claims 1
- MWUXSHHQAYIFBG-UHFFFAOYSA-N nitrogen oxide Inorganic materials O=[N] MWUXSHHQAYIFBG-UHFFFAOYSA-N 0.000 abstract description 9
- 230000005587 bubbling Effects 0.000 abstract description 2
- 230000003647 oxidation Effects 0.000 abstract 1
- 238000007254 oxidation reaction Methods 0.000 abstract 1
- 229910052778 Plutonium Inorganic materials 0.000 description 7
- 238000010531 catalytic reduction reaction Methods 0.000 description 7
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 7
- 230000000052 comparative effect Effects 0.000 description 4
- 238000004519 manufacturing process Methods 0.000 description 4
- 238000002360 preparation method Methods 0.000 description 4
- 239000003638 chemical reducing agent Substances 0.000 description 3
- 238000006722 reduction reaction Methods 0.000 description 3
- 229910002651 NO3 Inorganic materials 0.000 description 2
- NHNBFGGVMKEFGY-UHFFFAOYSA-N Nitrate Chemical compound [O-][N+]([O-])=O NHNBFGGVMKEFGY-UHFFFAOYSA-N 0.000 description 2
- IOVCWXUNBOPUCH-UHFFFAOYSA-N Nitrous acid Chemical compound ON=O IOVCWXUNBOPUCH-UHFFFAOYSA-N 0.000 description 2
- 229910004298 SiO 2 Inorganic materials 0.000 description 2
- 238000000605 extraction Methods 0.000 description 2
- 238000005984 hydrogenation reaction Methods 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 239000010970 precious metal Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 238000000746 purification Methods 0.000 description 2
- 238000004064 recycling Methods 0.000 description 2
- 238000007086 side reaction Methods 0.000 description 2
- 238000005979 thermal decomposition reaction Methods 0.000 description 2
- 230000009466 transformation Effects 0.000 description 2
- 229910018072 Al 2 O 3 Inorganic materials 0.000 description 1
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 1
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 238000003421 catalytic decomposition reaction Methods 0.000 description 1
- 238000005202 decontamination Methods 0.000 description 1
- 230000003588 decontaminative effect Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005868 electrolysis reaction Methods 0.000 description 1
- 239000012527 feed solution Substances 0.000 description 1
- 229910052737 gold Inorganic materials 0.000 description 1
- XLYOFNOQVPJJNP-ZSJDYOACSA-N heavy water Substances [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 1
- 239000012535 impurity Substances 0.000 description 1
- 150000002500 ions Chemical class 0.000 description 1
- HIPDIPCGFKENGR-UHFFFAOYSA-N nitric acid uranium Chemical compound [U].O[N+]([O-])=O HIPDIPCGFKENGR-UHFFFAOYSA-N 0.000 description 1
- 239000012074 organic phase Substances 0.000 description 1
- 239000002574 poison Substances 0.000 description 1
- 231100000614 poison Toxicity 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 238000005201 scrubbing Methods 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
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- C01—INORGANIC CHEMISTRY
- C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
- C01G43/00—Compounds of uranium
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- Y—GENERAL 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
Description
技术领域technical field
本发明涉及一种制备四价铀的工艺过程,特别是催化加氢还原硝酸铀酰(六价铀)制备硝酸铀(四价铀)的工艺过程。The invention relates to a technological process for preparing tetravalent uranium, in particular to a technological process for preparing uranium nitrate (tetravalent uranium) by catalytic hydrogenation reduction of uranyl nitrate (hexavalent uranium).
背景技术Background technique
随着核电大规模开发与应用,核乏燃料清洁处理与高效回收利用已经成为核电进一步发展的关键所在。目前,国内外后处理厂主要采用的技术为Purex工艺流程。在该工艺过程中首先通过萃取单元将有价值的铀钚元素萃取到有机相中,从而与绝大多数裂片元素分离,实现去污的目的;随后,加入四价铀作为还原剂,将四价钚还原为三价进入到水相中,但六价铀仍停留在油相中,从而实现铀钚高效分离纯化。该过程最大优点为,在将亲油性四价钚还原为亲水性的三价同时将新加入四价铀氧化为六价,这样实现了不引入任何杂质离子前提下,实现铀/钚清洁分离和高效利用。因此为了实现上述过程,除了应有的萃取工艺过程以外,开发一种六价铀还原生成四价铀的工艺过程和相关的反应设备,对于整个工艺开发和利用非常重要。With the large-scale development and application of nuclear power, the clean treatment and efficient recycling of nuclear spent fuel has become the key to the further development of nuclear power. At present, the technology mainly adopted by domestic and foreign reprocessing plants is the Purex process. In this process, the valuable uranium and plutonium elements are first extracted into the organic phase through the extraction unit, so as to be separated from most of the split elements to achieve the purpose of decontamination; then, tetravalent uranium is added as a reducing agent to convert the tetravalent uranium The plutonium is reduced to trivalent and enters the water phase, but the hexavalent uranium remains in the oil phase, thereby realizing the efficient separation and purification of uranium and plutonium. The biggest advantage of this process is that the lipophilic tetravalent plutonium is reduced to hydrophilic trivalent while the newly added tetravalent uranium is oxidized to hexavalent, thus realizing the clean separation of uranium/plutonium without introducing any impurity ions and efficient use. Therefore, in order to realize the above process, in addition to the proper extraction process, it is very important to develop a process for reducing hexavalent uranium to generate tetravalent uranium and related reaction equipment for the development and utilization of the entire process.
在目前我国技术中,四价铀制备主要依靠电解,制备出的料液中四价铀含量仅为75%(总铀浓度200g/l,四价铀浓度为150g/l)。低浓度四价铀导致我国目前后续工艺中钚的含量仅为3g/l(法国UP3,UP2-800为6g/l),这对后续钚纯化循环利用带来很大压力,增加系统负荷和处理费用。此外,中国原子能科学研究院也提出了硝酸肼催化还原硝酸铀酰制备硝酸铀工艺过程,该反应过程中硝酸肼除了与硝酸铀酰发生如(1)反应外,硝酸肼也能在催化剂作用下进行热分解反应(2)。在相关的反应器中,反应(1)与反应(2)是一个平行的反应过程,如果反应液停留时间不够,反应(1)不能完全进行,硝酸铀酰转化率相对较大,但当反应液停留时间过长,硝酸肼催化分解反应(2)过渡进行,使其产品液从还原态转变为氧化态,反应生成的四价硝酸铀进一步被氧化为六价硝酸铀酰,使得六价铀转化率降低。因此,为了在该过程中获得较高硝酸铀酰转化率,需较为准确地控制其反应液停留时间使其硝酸肼转化率在30%-40%,这种对反应器停留时间的特殊要求,给该过程的工业化带来了很大的困难。In the current technology in my country, the preparation of tetravalent uranium mainly relies on electrolysis, and the content of tetravalent uranium in the prepared feed solution is only 75% (total uranium concentration 200g/l, tetravalent uranium concentration 150g/l). Due to the low concentration of tetravalent uranium, the content of plutonium in the current follow-up process in my country is only 3g/l (France UP3, UP2-800 is 6g/l), which brings great pressure to the subsequent plutonium purification and recycling, increasing system load and processing cost. In addition, the China Institute of Atomic Energy also proposed a process for the preparation of uranium nitrate by catalytic reduction of uranyl nitrate with hydrazine nitrate. In this reaction process, in addition to the reaction with uranyl nitrate as in (1), hydrazine nitrate can also react with uranyl nitrate under the action of a catalyst. The thermal decomposition reaction (2) is carried out. In the relevant reactor, reaction (1) and reaction (2) are a parallel reaction process. If the residence time of the reaction solution is not enough, reaction (1) cannot be carried out completely, and the conversion rate of uranyl nitrate is relatively large, but when the reaction The liquid residence time is too long, and the catalytic decomposition reaction (2) of hydrazine nitrate is carried out transitionally, so that the product liquid changes from a reduced state to an oxidized state, and the tetravalent uranium nitrate generated by the reaction is further oxidized to hexavalent uranyl nitrate, making the hexavalent uranium nitrate. Conversion rates decrease. Therefore, in order to obtain a higher conversion rate of uranyl nitrate in this process, it is necessary to accurately control the residence time of the reaction solution so that the conversion rate of hydrazine nitrate is 30%-40%. This special requirement for the residence time of the reactor, It brings great difficulties to the industrialization of the process.
N2H5NO3+HNO3+2UO2(NO3)2=2U(OH)(NO3)3+2H2O+N2 (1)N2H5NO3 + HNO3 + 2UO2 ( NO3 )2 = 2U(OH)( NO3 )3 + 2H2O+ N2 ( 1 )
3N2H5NO3+HNO3=4NH4NO3+N2 (2)3N 2 H 5 NO 3 +HNO 3 =4NH 4 NO 3 +N 2 (2)
该专利公开的加氢催化还原过程中,氢气作为还原剂在催化剂的作用下发生如方程式(3)所示反应,从而将硝酸铀酰催化还原为硝酸铀。In the hydrogenation catalytic reduction process disclosed in this patent, hydrogen is used as a reducing agent to react as shown in equation (3) under the action of a catalyst, so that uranyl nitrate is catalytically reduced to uranyl nitrate.
UO2(NO3)2+HNO3+H2=U(OH)(NO3)3+H2O (3)UO 2 (NO 3 ) 2 +HNO 3 +H 2 =U(OH)(NO 3 ) 3 +H 2 O (3)
与硝酸肼催化还原相比,氢气催化还原不存在副反应,反应过程中还原剂H2是过量的,这样就可以增加反应液在反应器内的停留时间,保证六价铀的转化率大于98%,这样也降低了过程工业化的难度。在硝酸肼催化还原六价铀制备四价铀过程中,如果包括硝酸肼热分解反应(2),转化相同摩尔量硝酸铀酰几乎消耗相同摩尔量的肼和氢气,但每摩尔硝酸肼的费用高于氢气将近两个数量级,因此该工艺过程更具有经济性。Compared with hydrazine nitrate catalytic reduction, hydrogen catalytic reduction does not have side reactions, and the reducing agent H2 is excessive during the reaction process, which can increase the residence time of the reaction solution in the reactor and ensure that the conversion rate of hexavalent uranium is greater than 98%. , which also reduces the difficulty of process industrialization. In the process of preparing tetravalent uranium by catalytic reduction of hexavalent uranium with hydrazine nitrate, if the thermal decomposition reaction (2) of hydrazine nitrate is included, the conversion of the same molar amount of uranyl nitrate consumes almost the same molar amount of hydrazine and hydrogen, but the cost per mole of hydrazine nitrate It is nearly two orders of magnitude higher than hydrogen, so the process is more economical.
发明内容SUMMARY OF THE INVENTION
本发明的目的是提出一种制备四价铀的工艺过程。The purpose of the present invention is to propose a process for preparing tetravalent uranium.
为了实现上述目的,本发明提出了一种催化加氢还原硝酸铀酰(六价铀)制备硝酸铀(四价铀)的过程,其工艺流程为原料液储罐中硝酸铀酰和硝酸混合溶液和高压氢气储罐经计量泵和流量计计量后进入催化加氢反应器中,在催化剂与高压氢气的作用下六价铀被催化还原为四价铀,产品液与过量氢气的气液混合物离开反应器后,经在线滴加硝酸肼或肼后进入到高压气液分离器4中进行气液分离,其中气相混合物从分离器顶端流出进入到尾气吸收塔中将反应过程中产生的NOx经碱液吸收除去后加压循环后进入到高压氢气储气罐中循环备用,液相产品从分离器4的底部流出进入到产品液氢气置换塔中,在该塔中液相溶解氢经氮气置换去除后气相进入高放废气处理系统,液相作为产品进入下一个流程。In order to achieve the above purpose, the present invention proposes a process for preparing uranium nitrate (tetravalent uranium) by catalytic hydrogenation reduction of uranyl nitrate (hexavalent uranium), and the process flow is a mixed solution of uranyl nitrate and nitric acid in a raw material liquid storage tank And the high-pressure hydrogen storage tank is metered by the metering pump and flow meter into the catalytic hydrogenation reactor. Under the action of the catalyst and high-pressure hydrogen, the hexavalent uranium is catalytically reduced to tetravalent uranium, and the gas-liquid mixture of the product liquid and excess hydrogen leaves. After the reactor, after online dropwise addition of hydrazine nitrate or hydrazine, it enters the high-pressure gas-
该工艺过程所发生的主要反应为硝酸铀酰在催化剂的作用与氢气和硝酸反应生成硝酸铀,如公式(3)所示。此外,在反应过程中,我们需优化反应温度和反应器压力,来避免硝酸在催化剂的作用下催化还原为亚硝酸,如反应式(4)所示:The main reaction in this process is that uranyl nitrate reacts with hydrogen and nitric acid under the action of a catalyst to generate uranyl nitrate, as shown in formula (3). In addition, in the reaction process, we need to optimize the reaction temperature and reactor pressure to avoid the catalytic reduction of nitric acid to nitrous acid under the action of the catalyst, as shown in the reaction formula (4):
HNO3+H2=HNO2+H2O (4)HNO 3 +H 2 =HNO 2 +H 2 O (4)
亚硝酸进一步分解:Nitrous acid further decomposes:
2HNO2=NO+NO2+H2O (5)2HNO 2 =NO+NO 2 +H 2 O (5)
反应(5)生成的氮氧化物会对反应过程中的催化剂中毒。The nitrogen oxides produced in reaction (5) will poison the catalyst during the reaction.
其中储罐中原料液的组成(质量百分比):硝酸铀酰:5%-40%;硝酸:1%-20%;水:余量The composition (mass percentage) of the raw material liquid in the storage tank: uranyl nitrate: 5%-40%; nitric acid: 1%-20%; water: balance
在线滴加后气液混合物中硝酸肼和/或肼的终质量浓度为0%-10%(优选1%-5%,更优选1%-3%)。The final mass concentration of hydrazine nitrate and/or hydrazine in the gas-liquid mixture after the online dropwise addition is 0%-10% (preferably 1%-5%, more preferably 1%-3%).
其中催化加氢反应器可以是带有换热夹套的流化床、固定床或浆态床中的一种或多种组合,操作温度为-20-100摄氏度,操作压力为0.1-20Mpa(表压),优选2-20MPaWherein the catalytic hydrogenation reactor can be one or more combinations of a fluidized bed with a heat exchange jacket, a fixed bed or a slurry bed, the operating temperature is -20-100 degrees Celsius, and the operating pressure is 0.1-20Mpa ( Gauge pressure), preferably 2-20MPa
其中催化加氢反应器中的催化剂可以由Pt、Ru、Ir或Au中的一种或多种贵金属负载于SiO2、C或TiO2中的一种或多种氧化物(优选SiO2或TiO2中的一种或二种)载体上形成的负载型贵金属催化剂,其中贵金属负载量为0.01%-10%(优选1%-5%)。原料液储罐中的硝酸铀酰与硝酸混合后与循环氢气经反应器一端进入到装有催化剂的高压加氢反应器中,硝酸铀酰被氢气催化还原为硝酸铀,过量的氢气和产品硝酸铀经反应器另一端流出反应器。该气液混合物经在线滴加硝酸肼或肼溶液后进入到高压气液分离器分离,气相从分离器的顶部经解压后进入到气相尾气洗涤塔中,通过碱液将气相中的氮氧化物吸收分离,氢气经压缩机加压后进入到高压氢气储罐中,其中液相产品经分离器底部排除进入到常压液相产品氢气置换塔中,在该塔中通过使用氮气鼓泡装置将液相中的溶解氢去除,从而确保后续工艺的安全,所得气体进入到高放尾气的处理系统。Wherein the catalyst in the catalytic hydrogenation reactor can be supported by one or more noble metals in Pt, Ru, Ir or Au on one or more oxides in SiO 2 , C or TiO 2 (preferably SiO 2 or TiO 2 ) One or both of 2 ) a supported noble metal catalyst formed on a carrier, wherein the noble metal loading is 0.01%-10% (preferably 1%-5%). The uranyl nitrate and nitric acid in the raw material liquid storage tank are mixed with the circulating hydrogen and enter into the high pressure hydrogenation reactor equipped with catalyst through one end of the reactor. The uranyl nitrate is catalytically reduced by hydrogen to uranyl nitrate, excess hydrogen and product nitric acid Uranium flows out of the reactor through the other end of the reactor. The gas-liquid mixture enters the high-pressure gas-liquid separator after dropwise addition of hydrazine nitrate or hydrazine solution online, and the gas phase is decompressed from the top of the separator and then enters the gas-phase tail gas scrubbing tower. Absorption and separation, the hydrogen is pressurized by the compressor and then enters the high-pressure hydrogen storage tank, wherein the liquid-phase product is discharged through the bottom of the separator and enters the normal-pressure liquid-phase product hydrogen replacement tower, in which the nitrogen bubbling device is used in the tower. The dissolved hydrogen in the liquid phase is removed, thereby ensuring the safety of the subsequent process, and the obtained gas enters the treatment system of high-emission tail gas.
与现有技术相比,本发明具有的实质性特点是:Compared with the prior art, the substantial features that the present invention has are:
1、与电催化还原硝酸铀酰制备硝酸铀相比,其六价铀转化率可达98%以上;1. Compared with electrocatalytic reduction of uranyl nitrate to prepare uranium nitrate, the conversion rate of hexavalent uranium can reach more than 98%;
2、与硝酸肼催化还原制备四价铀相比,避免了相关副反应的发生,确保了六价铀转化率大于98%;2. Compared with the preparation of tetravalent uranium by catalytic reduction of hydrazine nitrate, it avoids the occurrence of related side reactions and ensures that the conversion rate of hexavalent uranium is greater than 98%;
3、与现有四价铀制备工艺相比,源于气转化率高,氢气成本低,有良好的经济性。3. Compared with the existing tetravalent uranium preparation process, the source gas conversion rate is high, the hydrogen cost is low, and it has good economy.
附图说明Description of drawings
图1为本发明工艺流程图;其中:1、原料液储罐;2、氢气储气罐;3、催化加氢反应器;4、高压气液分离罐;5、反应尾气吸收塔;6、产品液氢气置换塔;7、碱液储罐。Fig. 1 is a process flow diagram of the present invention; wherein: 1, raw material liquid storage tank; 2, hydrogen gas storage tank; 3, catalytic hydrogenation reactor; 4, high pressure gas-liquid separation tank; 5, reaction tail gas absorption tower; 6, Product liquid hydrogen replacement tower; 7, lye storage tank.
具体实施方式Detailed ways
采用的装置包括原料液储罐、氢气储气罐、催化加氢反应器、高压气液分离罐、反应尾气吸收塔,产品液氢气置换塔、吸收用碱液储罐;The devices used include raw material liquid storage tank, hydrogen gas storage tank, catalytic hydrogenation reactor, high-pressure gas-liquid separation tank, reaction tail gas absorption tower, product liquid hydrogen replacement tower, and lye storage tank for absorption;
原料液储罐中硝酸铀酰和硝酸混合溶液经流量计计量和高压氢气储罐的氢气经计量泵计量后进入催化加氢反应器中,在催化加氢反应器中负载型贵金属催化剂与氢气的作用下硝酸铀酰中的六价铀被催化还原为四价铀,产品液与过量(相对于硝酸铀酰)氢气的气液混合物离开催化加氢反应器后,经在线滴加硝酸肼和/或肼后进入到高压气液分离器(操作压力为4Mpa(表压))中进行气液分离,其中气相混合物从分离器顶端流出进入到反应尾气吸收塔中将反应过程中产生的NOx(X为1-2)经碱液(碱液为3M的氢氧化钠)吸收除去后加压循环后揉返回进入到氢气储气罐中循环备用,液相产品从气液分离器底部流出进入到产品液氢气置换塔中,在该塔中液相溶解氢经氮气置换去除后气相进入高放废气处理系统后直接放空,液相产物即为产品。The mixed solution of uranyl nitrate and nitric acid in the raw material liquid storage tank is metered by a flow meter, and the hydrogen in the high-pressure hydrogen storage tank is metered by a metering pump and then enters the catalytic hydrogenation reactor. Under the action of uranyl nitrate, the hexavalent uranium is catalytically reduced to tetravalent uranium. After the gas-liquid mixture of the product liquid and excess (relative to uranyl nitrate) hydrogen leaves the catalytic hydrogenation reactor, hydrazine nitrate and/or hydrazine nitrate are added dropwise online. Or hydrazine and then enter into the high-pressure gas-liquid separator (operating pressure is 4Mpa (gauge pressure)) for gas-liquid separation, wherein the gas-phase mixture flows out from the top of the separator and enters the reaction tail gas absorption tower to remove the NOx (X) produced in the reaction process. 1-2) After being absorbed and removed by the lye (the lye is 3M sodium hydroxide), it is pressurized and circulated and returned to the hydrogen gas storage tank for circulation backup, and the liquid-phase product flows out from the bottom of the gas-liquid separator and enters the product In the liquid hydrogen replacement tower, the liquid phase dissolved hydrogen in the tower is removed by nitrogen replacement, and then the gas phase enters the high emission waste gas treatment system and is directly vented, and the liquid phase product is the product.
于反应尾气吸收塔内的顶部设有碱液喷头,喷头经泵通过管路与碱液储罐相连,反应尾气吸收塔底部设有与碱液储罐相连的碱液回流管路。The top of the reaction tail gas absorption tower is provided with a lye liquid nozzle, which is connected to the lye liquid storage tank through a pump through a pipeline, and the bottom of the reaction tail gas absorption tower is provided with an alkaline liquid return pipeline connected to the lye liquid storage tank.
液氢气置换塔顶部设有尾气排放口。于反应尾气吸收塔顶部设有带阀门的尾气排放口。The top of the liquid hydrogen replacement tower is provided with a tail gas discharge port. A tail gas discharge port with a valve is arranged at the top of the reaction tail gas absorption tower.
实施例1Example 1
反应液处理量为62.5kg/h,原料液储罐中UO2(NO3)2的质量含量为0.31(31%),HNO3含量为0.1(10%)和H2O含量为0.59(59%),六价铀浓度为208g/L;在线滴加硝酸肼后,保证高压气液分离罐内硝酸肼的终质量含量为2%;催化剂为平均粒径为100微米的Pt/SiO2(贵金属负载量为1%)。反应器为流化床反应器。氢气的流量为180Nm3/h,反应器温度为30摄氏度压力为4.0Mpa(表压),出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为204g/L。The processing capacity of the reaction solution is 62.5kg/h, the mass content of UO 2 (NO 3 ) 2 in the raw material liquid storage tank is 0.31 (31%), the content of HNO 3 is 0.1 (10%) and the content of H 2 O is 0.59 (59%). %), the concentration of hexavalent uranium is 208g/L; after online dropwise addition of hydrazine nitrate, ensure that the final mass content of hydrazine nitrate in the high-pressure gas-liquid separation tank is 2 %; the catalyst is a Pt/SiO with an average particle size of 100 microns ( The precious metal loading is 1%). The reactor is a fluidized bed reactor. The flow rate of hydrogen is 180Nm 3 /h, the temperature of the reactor is 30 degrees Celsius, the pressure is 4.0Mpa (gauge pressure), the conversion rate of the outlet uranyl nitrate is 98%, and the content of tetravalent uranium in the product liquid is 204g/L.
实施例2Example 2
与实施例1不同在于(其余和过程与其相同),原料液储罐中UO2(NO3)2的质量含量为0.20(20%),HNO3含量为0.1(10%)和H2O含量为0.7(70%),六价铀浓度为134.2g/L,出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为131.5g/L。Different from Example 1 (the rest and process are the same), the mass content of UO 2 (NO 3 ) 2 in the raw material liquid storage tank is 0.20 (20%), the content of HNO 3 is 0.1 (10%) and the content of H 2 O is 0.7 (70%), the concentration of hexavalent uranium is 134.2g/L, the conversion rate of export uranyl nitrate is 98%, and the content of tetravalent uranium in the product liquid is 131.5g/L.
实施例3Example 3
与实施例2不同在于(其余和过程与其相同)原料液储罐中UO2(NO3)2的质量含量为HNO3含量为0.2(20%)和H2O含量为0.6(60%),六价铀浓度为134.2g/L,出口硝酸铀酰的转化率为98.1%,产品液中四价铀的含量为132g/L。The difference from Example 2 is that (the rest and process are the same) the mass content of UO 2 (NO 3 ) 2 in the raw material liquid storage tank is that the content of HNO 3 is 0.2 (20%) and the content of H 2 O is 0.6 (60%), The concentration of hexavalent uranium is 134.2g/L, the conversion rate of export uranyl nitrate is 98.1%, and the content of tetravalent uranium in the product liquid is 132g/L.
实施例4Example 4
与实施例2不同在于保证高压气液分离罐内硝酸肼的终质量含量为1%;出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为131.5g/L。The difference from Example 2 is that the final mass content of hydrazine nitrate in the high-pressure gas-liquid separation tank is guaranteed to be 1%; the conversion rate of the outlet uranyl nitrate is 98%, and the content of tetravalent uranium in the product liquid is 131.5 g/L.
实施例5Example 5
与实施例2不同在于(其余和过程与其相同)通过在线滴加硝酸肼和肼,保证高压气液分离罐内硝酸肼和肼的终质量含量为5%;出口硝酸铀酰的转化率为98.1%,产品液中四价铀的含量为132g/L。The difference from Example 2 is that (the rest and process are the same) by online dropwise addition of hydrazine nitrate and hydrazine to ensure that the final mass content of hydrazine nitrate and hydrazine in the high-pressure gas-liquid separation tank is 5%; the transformation rate of outlet uranyl nitrate is 98.1 %, the content of tetravalent uranium in the product liquid is 132g/L.
实施例6Example 6
与实施例2不同在于(其余和过程与其相同)反应器温度为-20摄氏度压力为2.0Mpa(表压),出口硝酸铀酰的转化率为98.1%,产品液中四价铀的含量为132g/L。The difference from Example 2 is that the reactor temperature is -20 degrees Celsius and the pressure is 2.0Mpa (gauge pressure), the conversion rate of the outlet uranyl nitrate is 98.1%, and the content of tetravalent uranium in the product liquid is 132g /L.
实施例7Example 7
与实施例2不同在于(其余和过程与其相同)反应器温度为-20摄氏度压力为8.0Mpa(表压),出口硝酸铀酰的转化率为98.1%,产品液中四价铀的含量为132g/L。The difference from Example 2 is that the reactor temperature is -20 degrees Celsius and the pressure is 8.0Mpa (gauge pressure), the conversion rate of the outlet uranyl nitrate is 98.1%, and the content of tetravalent uranium in the product liquid is 132g /L.
实施例8Example 8
与实施例2不同在于(其余和过程与其相同)反应器温度为40摄氏度,压力为20.0Mpa(表压),出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为131.5g/L。The difference from Example 2 is that the reactor temperature is 40 degrees Celsius, the pressure is 20.0Mpa (gauge pressure), the conversion rate of the outlet uranyl nitrate is 98%, and the content of tetravalent uranium in the product liquid is 131.5%. g/L.
对比例1Comparative Example 1
与实施例1相比其不同在于(其余和过程与其相同)反应温度为60摄氏度,出口硝酸铀酰的转化率为90%,产品液中四价铀的含量为188g/L,但由于反应过程中的温度较高使得反应(5)进行,大量氮氧化物的生成使其催化剂的活性在较短的时间内有明显地下降。Compared with Example 1, the difference is that (the rest and the process are the same) the reaction temperature is 60 degrees Celsius, the conversion rate of the outlet uranyl nitrate is 90%, and the content of tetravalent uranium in the product liquid is 188g/L, but due to the reaction process. The higher temperature makes the reaction (5) proceed, and the formation of a large amount of nitrogen oxides makes the activity of the catalyst decrease significantly in a short period of time.
对比例2Comparative Example 2
与实施例1相比,其不同在于(其余和过程与其相同)在线滴加后,保证高压气液分离罐内硝酸肼的终质量含量为0.1%,出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为120g/L,离开反应器后所生成的四价铀被硝酸进一步氧化为六价铀;Compared with Example 1, its difference is that (the rest and process are the same as it) after the online dropwise addition, it is guaranteed that the final mass content of hydrazine nitrate in the high-pressure gas-liquid separation tank is 0.1%, and the transformation efficiency of the outlet uranyl nitrate is 98%, The content of tetravalent uranium in the product liquid is 120g/L, and the tetravalent uranium generated after leaving the reactor is further oxidized to hexavalent uranium by nitric acid;
对比例3Comparative Example 3
与实施例1相比,其不同在于(其余和过程与其相同)原料液储罐中UO2(NO3)2的质量含量为0.31(31%),HNO3含量为0.02(2%)和H2O含量为0.67(67%),由于转化过程中硝酸的浓度不够,使其出口硝酸铀酰的转化率为75%,产品液中四价铀的含量为156g/L;Compared with Example 1, the difference lies in that (the rest and process are the same) the mass content of UO 2 (NO 3 ) 2 in the raw material liquid storage tank is 0.31 (31%), the content of HNO 3 is 0.02 (2%) and H The 2 O content is 0.67 (67%), due to the insufficient concentration of nitric acid in the conversion process, the conversion rate of the export uranyl nitrate is 75%, and the content of tetravalent uranium in the product liquid is 156g/L;
对比例4Comparative Example 4
与实施例1相比,其不同在于(其余和过程与其相同)催化剂为平均粒径为100微米的Pt/Al2O3(贵金属负载量为1%),出口硝酸铀酰的转化率为98%,产品液中四价铀的含量为204g/L,但反应过程中源于氧化铝溶解使其硝酸铀酰的转化率随着反应的进行由明显地下降。Compared with Example 1, the difference is that (the rest and the process are the same) the catalyst is Pt/Al 2 O 3 (the precious metal loading is 1%) with an average particle size of 100 microns, and the conversion rate of the outlet uranyl nitrate is 98 %, the content of tetravalent uranium in the product solution was 204g/L, but the conversion rate of uranyl nitrate decreased significantly with the progress of the reaction due to the dissolution of alumina during the reaction.
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Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB884666A (en) * | 1959-01-29 | 1961-12-13 | Atomic Energy Commission | Improved process for the preparation of uranium tetrafluoride from uranium dioxide |
US6759027B1 (en) * | 1999-06-17 | 2004-07-06 | Compagnie Generale Des Matieres Nucleaires | Method and installation for carrying out a three phase chemical reaction under pressure |
CN102249331A (en) * | 2011-04-19 | 2011-11-23 | 中国原子能科学研究院 | Preparation method of tetravalent uranium solution |
CN106311092A (en) * | 2016-11-02 | 2017-01-11 | 中国原子能科学研究院 | Catalytic device for preparing U(IV) solution |
CN106458597A (en) * | 2014-06-13 | 2017-02-22 | 沙特基础工业全球技术公司 | Syngas production from binary and ternary cerium-based oxides |
-
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Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
GB884666A (en) * | 1959-01-29 | 1961-12-13 | Atomic Energy Commission | Improved process for the preparation of uranium tetrafluoride from uranium dioxide |
US6759027B1 (en) * | 1999-06-17 | 2004-07-06 | Compagnie Generale Des Matieres Nucleaires | Method and installation for carrying out a three phase chemical reaction under pressure |
CN102249331A (en) * | 2011-04-19 | 2011-11-23 | 中国原子能科学研究院 | Preparation method of tetravalent uranium solution |
CN106458597A (en) * | 2014-06-13 | 2017-02-22 | 沙特基础工业全球技术公司 | Syngas production from binary and ternary cerium-based oxides |
CN106311092A (en) * | 2016-11-02 | 2017-01-11 | 中国原子能科学研究院 | Catalytic device for preparing U(IV) solution |
Non-Patent Citations (1)
Title |
---|
"Catalytic reduction of U(VI) to U(IV) using hydrogen with platinum loaded on alumina and silica";Sahu, Avinash et al.;《JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY》;20141231;第163-167页 * |
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