Al2O3色层法从低浓铀靶件中分离99Mo条件研究

Investigation on Separation of 99Mo from Low Enriched Uranium Target by Al2O3 Chromatography

  • 摘要: 在裂变99Mo的生产工艺中,常用Al2O3色层法分离纯化99Mo。为建立Al2O3色层法从低浓铀(LEU)靶件中分离裂变99Mo的工艺,考察吸附时间、温度、酸度、预处理方式等对Al2O3吸附Mo效果的影响。研究采用Al2O3色层法从不同浓度HNO3溶液中分离Mo。测定Al2O3色层法对Al和主要杂质元素Sr、Ru、Zr、Te、Cs、I的去污系数。研究结果表明,在0.05~0.1 mol/L HNO3介质中Al2O3对Mo有出色的吸附性能,Mo吸附率在99%以上,在NH4OH溶液中Al2O3不吸附Mo。经500 ℃活化3 h预处理得到的Al2O3-C具有更大的比表面积,且在HNO3浓度大于0.1 mol/L时相比于150 ℃活化3 h预处理得到的Al2O3-B以及未经高温预处理得到的Al2O3-A对于Mo有更好的吸附性能。采用该工艺,通过Al2O3色层法从模拟的LEU靶件溶液中提取Mo,Mo回收率大于90%,Al2O3色层法对裂变杂质元素Ru、Sr、Zr、Te、Cs等的去除率均大于99.99%,对131I的去除率大于92%。由此可见,Al2O3在HNO3介质中对Mo的吸附率高,能够有效地去除99Mo产品中的杂质核素,适用于从低浓铀靶件中分离裂变99Mo。

     

    Abstract: Al2O3 chromatography is usally used for separation and purification of 99Mo in the production process of fission 99Mo. To establish the separation process for fission 99Mo from low enriched uranium (LEU) target by Al2O3 chromatography, the effect of 99Mo adsorption on acidic Al2O3 with different conditions of time, temperature, concentration of nitric acid and pretreatment method of Al2O3 were studied. Decontamination effectiveness of major impurities including Sr, Ru, Zr, Te, Cs and I with Al2O3 chromatographic method was evaluated. From experimental results, strong adsorption (more than 99%) of Mo on Al2O3 in 0.05-0.1 mol/L HNO3 solution was observed and no adsorption happened in NH4OH solution. The Al2O3-C activated at 500 ℃ for 3 h had a larger specific surface area than those of Al2O3-B activated at 150 ℃ for 3 h and Al2O3-A pretreated at 60 ℃. In addition, Al2O3-C had a better adsorption performance for Mo than Al2O3-B and Al2O3-A in HNO3 solution with concentration greater than 0.1 mol/L, the recovery yield of Mo was more than 90% using Al2O3 chromatography. The decontamination effectiveness of the impurities Ru, Sr, Zr, Te and Cs was more than 99.99% and more than 92% of 131I could be removed by Al2O3 chromatography. Al2O3 has high adsorption rate, fast adsorption rate and large adsorption capacity for Mo in HNO3 solution, which can effectively remove impurities from fission 99Mo. It is suitable for the separation process of fission 99Mo from low enriched uranium target.

     

/

返回文章
返回