Determination of 14C in activated metal waste Original Research Article

The inherent radioactivity and potential toxicity of nuclear waste provide challenges to persons responsible for its characterization. Specifically, this paper describes the development of an analytical method quantitatively to measure 14C in radioactive waste. A separation from other beta-emitting radionuclides is first required before the weak beta radiation of 14C can be counted using liquid scintillation. Hence, this paper discusses the development of a modified, remote carbon analyzer which has provided a means to perform this separation. This modified technique is much easier than the difficult and time consuming techniques traditionally used for determining 14C concentrations. The carbon analyzer (LECO® HF-400/IR-412 carbon analyzer) that was modified for remote operation in the Argonne National Laboratory — West (ANL-W) Analytical Laboratory Hot Cells (ALHC) has been used to separate and isolate 14C from other beta-emitting radionuclides in samples of different matrices. These include irradiated beryllium from the Advanced Test Reactor (ATR) located on the Idaho National Environmental and Engineering Laboratory (INEEL) and samples of stainless steel that were irradiated in the Experimental Breeder Reactor II.