Showing papers by "National Defence University, Pakistan published in 2000"
01 Jan 2000
TL;DR: In this article, a combined separation method was used for the detection of radiostrontium (89Sr and 90Sr) and of 90Y in low-and intermediate-level radioactive liquid waste samples from the Paks Nuclear Power Plant.
Abstract: This paper reports on the method, results, and experiences of the 89Sr and 90Sr analysis performed on low-and intermediate-level radioactive liquid waste samples from the Paks Nuclear Power Plant. The analysis is based on a combined separation method, which results in the separation and detection of radiostrontium (89Sr and 90Sr) and of 90Y. After the suitable pretreatment of the samples, radiostrontium is concentrated using the Sr-Spec® (EIChroM Industries, Darien, IL, 60561 USA) chromatographic column. The eluted radiostrontium is precipitated in a thin layer and its activity measured by a low-background, gamma-ray-compensated, alpha-beta detector. The chemical yield is determined by atomic emission spectroscopy. The 90Y activity of the samples is also measured by the procedure described elsewhere. This measurement is based on the selective adsorbing property of the yttrium-ammonium-oxalate and the yttrium-oxalate double salt mixture of yttrium. Under the proper conditions (pH, oxalate anion activity, mass ratio of the salts) the quantitative yield of 90Y can be achieved, as determined by using the 88Y inner standard. As a result, the radioactive concentration of 90Sr in the samples could be calculated. It was concluded that 89Sr was not present in the samples because of the relatively long (in years) storage life of these samples. However, this combined method can be easily adapted to matrices sampled at nuclear test sites.