辐照后核燃料中钚的放化分析

    RADIOCHEMICAL ANALYSIS OF PLUTONIUM IN IRRADIATED FUELS

    • 摘要: 本文研究了不需外加钚标准的放化-α谱法测定钚同位素浓度的方法。铀元件溶解液中钚用三异辛胺萃取、抗坏血酸反萃,直接在反萃液中电沉积制源,电沉积率达(100.0±0.5)%,因而使全程序钚的回收率稳定在(98.5±0.5)%。方法简便、灵敏(取钚量~0.2微克)。一根元件切片后测钚同位素浓度,沿轴向分布有对称关系,与已知的燃耗值(~(148)Nd)有线性关系。

       

      Abstract: In the determination of the concentration of plutonium isotopes in irradiated U-rods by radiochemical-alpha spectrometry, a stable chemical yield of (98.5±0.5)% of Pu can be obtained if the purification of plutonium is carried out by the extraction with TiOA followed by quantitative electro-deposition directly from back extraction solution with ascorbic acid. When the irradiated uranium rod is cut into pieces, the plutonium concentrations from diffrent pieces show a axially symmetric distribution and a linear relation with known fuel burn up (148Nd). This method needs only a sample of-0.2 μg Pu and the addition of a standard solution of 242Pu is not required.

       

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