反应堆辐照元件中锝的测定
MEASUREMENT OF TECHNETIUM IN THE SPENT FUEL
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摘要: <正> 一、前言 核燃料燃耗的测定是极为重要的,历年来作为燃耗监测体的有~(99)Mo,~(137)Cs,~(144)Ce,~(148)Nd和~(99)Tc等,其中~(99)Tc是60年代以来就受到重视的一个。 在铀的裂变产物中质量链为99的仅见~(99)Tc的寿命较长。而且~(99)Tc具有高裂变产额,因此在堆温小于1400℃时它是一个较好的燃耗监测体。 有关锝的分析方法文献中作了较为详细的介绍。为了准确测定核燃料元件溶解液中的~(99)Tc,首先应将Tc与大量放射性元素分离,其中Foster Jr R.E.等提出了一个Abstract: The extraction-spectrophotometrical determination (with the precision of±1%)of technetium, which recovery is about more than 96%, is described. First Tc inthe NaOH-Na_2CO_3 solution of fission products is extracted into the 2,6-dimethyl-pyridine and reextracted into H_2SO_4 solution from the organic phase by theaddition of CCl_4, then Tc is extracted into tetra-alkyl-ammonium(7402)-n-butylchloride phase by in order to be purified and spectrophotometric determinated.The n-butyl chloride phase contacts with H_2SO_4 solution containing KSCN andbecome purplish red. The colored complex with peak of absorption at 512 nm. hasa molar absorptivity of 5×10~4, and is stable for several hours. Of over 20common metals are studied, none interferes for the spectrophotometricdetermination of Tc. The results of Tc determination of 8 samples from spent fuel elements are incoincidence with the monitor of ~(148)Nd for burnup determination.
- Keywords:
- Technetium ,
- Exraction ,
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[1] Schwochav, K., The Analytical Chemistry of Technetium Top Curr. Chem.,96,110(1981). [2] 张绪立,裂变产物分析,第十三章锝,北京,原子能出版社,1995. [3] Foster,Jr R.E et al,Anal Chem,39,563(1967). [4] 张绪立等,原子能科学技术(2), 169(1976) . [5] 张绪立等,原子能科学技术(1), 24(1975) . [6] 张绪立等,原子能科学技术(1), 101(1976) . [7] 张绪立等,原子能科学技术(1), 53(1976) . [8] Rimshaw,S J. et al., Anal Chem,33,751(1961). [9] 张丕禄等,原子能科学技术,23(4), (1989) 。
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