Hostname: page-component-586b7cd67f-vdxz6 Total loading time: 0 Render date: 2024-11-29T07:23:19.507Z Has data issue: false hasContentIssue false
  • English
  • Français

Conceptual Model for Deriving the Repository Source Term

Published online by Cambridge University Press:  26 February 2011

D. H. Alexander ,
M. J. Apted ,
A. M. Liebetrau ,
A. E. Van Luik ,
R. E. Williford  and
P. G. Doctor
D. H. Alexander
Affiliation:
U. S. Department of Energy, Washington, D.C., 20545
M. J. Apted
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, Washington, 99352
A. M. Liebetrau
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, Washington, 99352
A. E. Van Luik
Affiliation:
Roy F. Weston, Inc./Rogers & Assoc. Engineering Corp., 2301 Research Blvd., Rockville, Maryland, 20850
R. E. Williford
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, Washington, 99352
P. G. Doctor
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, Washington, 99352
Get access

Abstract

Part of a strategy for evaluating the compliance of geologic repositories with Federal regulations is a modeling approach that would provide realistic release estimates for a particular configuration of the engineered-barrier system. The objective is to avoid worst-case bounding assumptions that are physically impossible or excessively conservative and to obtain probabilitistic estimates of (1) the penetration time for metal barriers and (2) radionuclide-release rates for individually simulated waste packages after penetration has occurred. The conceptual model described in this paper will assume that release rates are explicitly related to such time-dependent processes as mass transfer, dissolution and precipitation, radionuclide decay, and variations in the geochemical environment. The conceptual model will take into account the reduction in the rates of waste-form dissolution and metal corrosion due to a buildup of chemical reaction products. The sorptive properties of the metal-barrier corrosion products in proximity to the waste form surface will also be included. Cumulative releases from the engineered-barrier system will be calculated by summing the releases from a probabilistically generated population of individual waste packages.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 439
Copyright
Copyright © Materials Research Society 1985

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

[1] U.S. Environmental Protection Agency, Federal Register 47 (250): 58196–58206 (Proposed 40 CFR 191) (December 1982).Google Scholar
[2] U.S. Nuclear Regulatory Commission, 10 CFR 60, Federal Register 48 (120): 28194–28229 (June 1983).Google Scholar
.[3] Lester, D. H.. et al., ONWI-211, Science Applications, Inc. for Battelle Memorial Institute, Office of Nuclear Waste Isolation, Columbus, OH (1982).Google Scholar
[4] INTERA Environmental Consultants, Inc., ONWI-452, Battelle Memoria Institute, Office of Nuclear Waste Isolation, Columbus, OH (1983).Google Scholar
[5] Lyon, R. B.., In: Topp, S. V. (Ed.), Scientific Basis for NuclearWaste Management, Mat. Res. Soc. Symp. Proc. Vol.16, Elsevier, New York (1982).Google Scholar
[6] Dormouth, K. W. and Quick, R. D., International Journal of Energy Systems, 1:125 (1981).Google Scholar
[7] SKBF, Swedish Nuclear Fuel Supply Company, KBS-3, S-102 48, Vols. 3 and 4, Stockholm, Sweden (1983).Google Scholar
[8] Sagar, B., Eslinger, P. W., and Baca, R. G., Draft RHO-BW-ST-68P, Rockwell Hanford Operations, Richland, WA (1984).Google Scholar
[9] U.S. Department of Energy, DOE/ET-0028, U.S. Dept. of Energy Office of Nuclear Waste Management, Washington, DC, Vol. 1: 3.3.47 (May 1979).Google Scholar
[10] Meyer, R. E., Arnold, W. D., and Case, F. I., NUREG/CR-3389, ORNL-5978, Oak Ridge National Laboratory, Oak Ridge, TN, p. 19 (February 1984).Google Scholar
[11] Couture, R. A., and Seitz, M. G., Nuclear and Chemical Waste Management, 4:301–306 (1983).CrossRefGoogle Scholar
[12] Rickertsen, L. D. and Luik, A. E. Van, Paper presented at OECD Workshop on the Source Term for Radionuclide Migration from High-Level Waste or Spent Nuclear Fuel under Realistic Repository Conditions, Albuquerque, New Mexico, November 13–15, 1984.Google Scholar
[13] Dayal, R. et al., NUREG/CR-2333, Task 1, Brookhaven National Laboratory for U.S. NRC Office of Nuclear Material Safety and Safeguards, Washington, DC, p. 96 (1982).Google Scholar
[14] Office of Nuclear Waste Isolation, BMI/ONWI-545, Battelle Memorial Institute, Columbus, OH (1984).Google Scholar