Abstract
Abstract This report describes a calculation equation for radioactivity determination, and sample pretreatment based on the fundamental design mentioned in previous report (Na79), which satisfied the guide for dose assessment objectives for a light-water-cooled nuclear power reactor (AECJ75). The effect of the sample pretreatment on the determination of half the level of needed determination limit (NDL} (Na79) was evaluated using a commercially available Ge(Li) detector system. It was clarified that pretreatment should be carried out for environmental samples up to 8301. of the initial sample amount. The most suitable radioactivity determination method with a commercially available Ge(Li) detector system far dose assessment is presented herein.
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