Low level Pu and Am estimation in liquid waste from nuclear reactor

Estimation of very low amount up to pico-gram of Am and Pu in the liquid waste of U-Pu fuel cycle of the irradiated U fuel from the nuclear reactor has been carried out using combined method of α- and γ-ray spectrometric techniques. 241Am was estimated by γ-ray spectrometry from a plancheted source. In spite of the same α energy of 5.49 MeV for 241Am and 238Pu, the amount 238Pu was estimated by α spectrometry from the same plancheted source after subtracting amount of the 241Am obtained from γ-ray spectrometry. The amount of Am and Pu obtained by this technique is found to be superior compared to other techniques even in the presence of Th, U and fission products. (author)