ans <isperse solids. Treal volume L2 tealur2ed 2-i 2 200 ml alicnon is then drawn for gamma analysis. 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 tocal volume was analyzed for 90... _ 90. The sample is acidified to a pH of 1, stable strontium and yttrium carrier along with 89 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 904 precipitate which is used to determine the 905, urine activity concentration. Sampie results are corrected for chemical yield and radiological decay of 90, post separation from 905, Because of the dura- tion between sample collection and sample analysis (in excess of two months) 90, and 90 . eget . . Sr are in secular equilibrium at time of sample analysis. 13765 and 905, urine activity concentrations for all pooled sam- ples are reported in Table l. 137 Cs and 7] “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 detween 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 transuranic analyses were carried out by alpha spectroscopy. mum detectable limit was 3.7 x 10° Bq for all analysis systems. The mini-