ar i 4isperse sciids. Trtal volume is rea_ur2ed eri a 200 drawn for gamma analysis. ml alicneh is rhen Gamma spectroscopy is performed with a 125 ce active volume, 26% relative efficiency Ge(Li) detector which is connected to a computer based multi-channel analyzer. Samples were counted from 4000 to 10000 seconds depending on the activity in the sample. When gamma analysis was completed, the aliquot was returned to the initial sample and the total volume was analyzed for 90. . 90, The sample is acidified to a pH of 1, stable strontium and yttrium carrier along with $5 5. tracer are added to the sample. The sample is chemi- cally processed according to the procedure reported in Appendix A. The final processing step results in a 90y precipitate which is used to determine the 905, urine activity concentration. Sample results are corrected for chemical yield and radiological decay of 904 post separation from 905,, Because of the dura~ tion between sample collection and sample analysis (in excess of two months) 90y and 90 . tage : . Sr are in secular equilibrium at time of sample analysis. 13764 and 905, urine activity concentrations for all pooled sam- ples are reported in Table l. 137 Cs and ” “Sr urine activity concentrations and the 905, body burden at time of removal are reported in Tables 2 through 5 for Bixini Atoll residents sampled osetween 1973 and 1980. The 705, data were used to calculate the bone marrow dose-equivalent commitment. Five day urine samples were also collected from 1974 to 1978. These samples were analyzed by Battelle Northwest Laboratory (BNWL), Environmental Monitoring Laboratory (EML) and Los Alamos Scientific Laboratory (LASL) for fission products and transuranic nuclides. 6. The results are presented in Table All transuraniec analyses were carried out by alpha spectroscopy. mum detectable limit was 3.7 x 10 - Bq for all analysis systems. The mini-