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作 者:吴宇轩 梁积新[1] 黄文博 向学琴[1] 沈亦佳[1] 于宁文[1] 吴如雷 赵婧妍 罗志福[1] WU Yuxuan;LIANG Jixin;HUANG Wenbo;XIANG Xueqin;SHEN Yijia;YU Ningwen;WU Rulei;ZHAO Jinyan;LUO Zhifu(Department of Nuclear Technology and Application,China Institute of Atomic of Energy,Beijing 102413)
机构地区:[1]中国原子能科学研究院核技术综合研究所,北京102413
出 处:《同位素》2021年第6期509-517,共9页Journal of Isotopes
基 金:国防科工局“十三五”核能开发科研第六批项目(后补助);核技术创新联合基金(U1967216)。
摘 要:为评价γ辐照对AG1-×8树脂吸附^(99)Mo的影响,选择吸收剂量分别为37.5、275、825 kGy的AG1-×8树脂,通过静态和动态实验,研究AG1-×8树脂对Mo(Ⅵ)的吸附性能。结果表明,经γ辐照后,AG1-×8树脂表面形态未发生变化及破损;AG1-×8树脂对Mo(Ⅵ)的静态分配系数随吸收剂量的增加而减小;AG1-×8树脂辐照前后对Mo(Ⅵ)的静态分配系数在NH_(4)OH介质中不随介质浓度变化,而在硝酸、氢氧化钠、碳酸铵介质中随浓度的增加而减小;在1 mol/L氨水介质中,AG1-×8树脂辐照前后对Mo(Ⅵ)吸附行为符合Langmuir等温模型,吸附过程为自发、吸热过程,饱和吸附容量分别为74.07、71.02、70.97、57.57 mg/g;Mo(Ⅵ)在NH_(4)OH中吸附、用1 mol/L碳酸铵溶液解吸,Mo(Ⅵ)回收率随吸收剂量的增大而降低。To evaluate the influence of gamma irradiation on adsorption of ^(99)Mo on AG1-×8 resin,three irradiated AG1-×8 resin with absorbed doses of 37.5 kGy,275 kGy and 825 kGy were chosen to investigate the adsorption properties of Mo(Ⅵ)on AG1-×8 resin via the static absorption and the dynamic adsorption experiments.The experimental results showed that no difference of the surface of AG1-×8 resin was observed compared to non-irradiated resin.The static distribution coefficient of Mo(Ⅵ)adsorbed by resin decreased with the increase of absorbed doses,and the static distribution coefficient of Mo(Ⅵ)adsorbed by irradiated and non-irradiated resin was not variable in different concentration of NH_(4)OH but decreased with increasing the concentration of HNO_(3),NaOH,and(NH_(4))_(2)CO_(3).The sorption on irradiated and non-irradiated resin both followed Langmuir isotherm model,indicating that each of these adsorption processes was spontaneous and endothermic in nature,and the static saturated adsorption capacity was 74.07 mg/g,71.02 mg/g,70.97 mg/g and 57.57 mg/g in 1 mol/L NH_(4)OH,respectively.While Mo(Ⅵ)was adsorbed in NH_(4)OH and desorbed with 1 mol/L(NH_(4))_(2)CO_(3),the recovery yield of Mo(Ⅵ)decreased with the increase of absorbed doses.
分 类 号:TL922[核科学技术—核燃料循环与材料]
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