Laboratory Evaluation of Colloid Transport Under Simulated Subsurface Conditions at the Waste Isolation Pilot Plant (WIPP): 2. Large-Scale-Intact-Core Column Flow Experiments
The Waste Isolation Pilot Plant (WIPP), located approximately 42 km southeast of Carlsbad, New Mexico, is being developed by the U.S. Department of Energy (DOE) as a disposal facility for transuranic waste produced by defense nuclear weapons programs. Regulations promulgated by the (1985) place limits on the cumulative radioactive release to the accessible environment over 10,000 years and require performance assessments to demonstrate WIPP compliance with regulatory standards. The only credible mechanisms for escape of radionuclides to the environment involve a breach of the repository during drilling for natural resources. The brines present in the repository, together with drilling mud and cuttings, may be transported through intrusion boreholes to a overlying transmissive carbonate rock unit, the Culebra Dolomite Member of the Rustler Formation, or directly to the surface, by pressurized fluids in the repository. Performance assessment calculations have shown that thorium, uranium, neptunium, plutonium, and americium are the most significant radionuclides in terms of total release of activity.
KeywordsFulvic Acid Sandia National Laboratory Colloid Transport Waste Isolation Pilot Plant Step Injection
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- Lucero, D. A., F. Gelbard, Y. K. Behl, and J. A. Romero. 1995. Test Plan for Laboratory Column Experiments for Radionuclide Adsorption Studies of the Culebra Dolomite Member of the Rustler Formation at the WIPP Site. WIPP Test Plan, TP 95-03. WPO#22640-October 12, 1994. Sandia National Laboratories, Albuquerque, NM.Google Scholar
- Papenguth, H. W., and Y. K. Behl. 1996. Test Plan for Evaluation of Colloid-Facilitated Actinide Transport at the Waste Isolation Pilot Plant. WIPP Test Plan, TP 96-01. WPO#31337. Sandia National Laboratories, Albuquerque, NM.Google Scholar
- Parker, J. C., and M. T. van Genuchten. 1984. Determining Transport Parameters from Laboratory and Field Tracer Experiments. Virginia Agricultural Experiment Station Bulletin VAESB 84-3. Virginia Agricultural Experiment Station, Blacksburg, VA.Google Scholar
- US Environmental Protection Agency. 1985. “Environmental Standards for the Management and Disposal of Spent Nuclear Fuel, High-Level, and Transuranic Radioactive Waste; Final Rule, 40 CFR Part 191,” Federal Register 50: 38066–38089.Google Scholar
- Yelton, W. G., Y. K. Behl, J. W. Kelley, M. Dunn, J. B. Gillow, A. J. Francis, H. W. Papenguth. 1996. Laboratory evaluation of colloidal actinide transport at the Waste Isolation Pilot Plant (WIPP): 1. Crushed-dolomite column flow experiments, in Experimental and Modeling Studies of Radionuclide Speciation in Real Systems, D. T. Reed, S. Clark and L. Ruo (eds), Plenum Publishing Corp., NY.Google Scholar