title: Interpretation of actinide-distribution data obtained from non-destructive and destructive post-test analyses of an intact-core column of Culebra dolomite.
abstract: The US Department of Energy (DOE), with technical assistance from Sandia National Laboratories, has successfully received EPA certification and opened the Waste Isolation Pilot Plant (WIPP), a nuclear waste disposal facility located approximately 42 km east of Carlsbad, NM. Performance assessment (PA) analyses indicate that human intrusions by inadvertent, intermittent drilling for resources provide the only credible mechanisms for significant releases of radionuclides from the disposal system. For long-term brine releases, migration pathways through the permeable layers of rock above the Salado formation are important. Major emphasis is placed on the Culebra Member of the Rustler Formation because this is the most transmissive geologic layer overlying the WIPP site. In order to help quantify parameters for the calculated releases, radionuclide transport experiments have been carried out using intact-core columns obtained from the Culebra dolomite member of the Rustler Formation within the WIPP site. This paper deals primarily with results of analyses for 241Pu and 241Am distributions developed during transport experiments in one of these cores. Transport experiments were done using a synthetic brine that simulates Culebra brine at the core recovery location (the WIPP air-intake shaft (AIS)). Hydraulic characteristics (i.e., apparent porosity and apparent dispersion coefficient) for intact-core columns were obtained via experiments using the conservative tracer 22Na. Elution experiments carried out over periods of a few days with tracers 232U and 239Np indicated that these tracers were weakly retarded as indicated by delayed elution of the species. Elution experiments with tracers 241Pu and 241Am were attempted but no elution of either species has been observed to date, including experiments of many months' duration. In order to quantify retardation of the non-eluted species 241Pu and 241Am after a period of brine flow, non-destructive and destructive analyses of one intact-core column were carried out to determine distribution of these actinides in the rock. Analytical results indicate that the majority of the 241Am remained very near the injection surface of the core (possibly as a precipitate), and that the majority of the 241Pu was dispersed with a very high apparent retardation value. The 241Pu distribution is interpreted using a single-porosity advection-dispersion model, and an approximate retardation value is reported.
authors: WIPP Regulatory Compliance Department, Sandia National Laboratories, Albuquerque, NM 87185-1395, USA. wgperki@sandia.gov
authors: W G
authors: WG
authors: Perkins
authors: D A
authors: DA
authors: Lucero
mesh_terms: D008671:Actinoid Series Elements / Q000032:analysis*; D002119:Calcium Carbonate / Q000032:analysis / Q000737:chemistry*; D005844:Geology / Q000379:methods; D006077:Government Agencies; D006801:Humans; D008274:Magnesium / Q000032:analysis / Q000737:chemistry*; D008903:Minerals / Q000737:chemistry; D011834:Radiation Monitoring / Q000379:methods*; D011850:Radioactive Waste; D011868:Radioisotopes / Q000032:analysis*; D014481:United States
chemical_list: D008671:Actinoid Series Elements; D008903:Minerals; D011850:Radioactive Waste; D011868:Radioisotopes; D002119:Calcium Carbonate; D008274:Magnesium; C028042:calcium magnesium carbonate