Abstract
Gamma scintillation spectrometry is used as a basis for the quantitative determination of absolute disintegration rate values for I131, I132, I133, I134, I135, Ba139, Ba140, Sr91 and Sr92 collected from reactor effluent air on activated coconut charcoal. After chemical separations for the various elements have been made, the complex γ-spectra resulting are treated mathematically, resulting in the solution of simultaneous linear equations to yield d/m values for the specific isotope. Corrections are made for any absorber between the source and NaI(Tl) crystal, for the total absolute detection efficiency for the counting geometry used, for the peak to total ratios for the particular photopeak, for the decay scheme, and for any internal conversion, thus obviating the need for standard plates of the isotope in question. The method is applicable to γ-emitters in general, providing values for corrections to be applied are available.
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