【摘要】 建立了N-苯甲酰-N-苯胲(BPHA)萃取、氨水反萃、结合2次α-安息香肟萃取除Mo、从某元件溶解液中分离93Nbm和94Nb的分离流程。该流程对137Cs和93Mo的去污因子分别为2.4×106和1×103,对144Ce和103Ru的去污因子大于104。采用宽能HPGeγ谱仪对产品进行测量。利用241Am、137Cs、57Co标准源得到仪器在低能部分的效率曲线,内插法得到对93Nbm(16.6 keV)的探测效率为(3.24±0.06)%,并最终确定了某元件溶解液中93Nbm的比活度为(126.87±4.86)Bq/g,94Nb的比活度小于0.05 Bq/g。更多还原

【Abstract】 A radiochemical procedure for separation of 93Nbm,94Nb from dissolution of spent fuel based on extraction using BPHA,back-extraction using ammonia,and extraction twice by α-benzoin oxime to remove 93Mo is developed.The procedure has decontamination factors of 2.4×106,1×103 to 137Cs,93Mo respectively and better than 104 to 144Ce and 103Ru.The efficiency curve at low energy region of broad energy Ge detector was calibrated using standard source of 241Am,137Cs and 57Co.So the efficiency of 93Nbm can be known from the curve.Finally,using this detection method and the procedure described before,the 93Nbm radioactivity in one kind of spent fuel dissolution is determined to be(126.87±4.86) Bq/g,and the specific activity of 94Nb is less than 0.05 Bq/g.更多还原