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Simulation of Radionuclide Migration in Groundwater Away From an Underground Nuclear Test

Published online by Cambridge University Press:  10 February 2011

A.F.B. Tompson ,
C.J. Bruton ,
W.L. Bourcier ,
D.E. Shumaker ,
A.B. Kersting ,
D.K. Smith ,
S.F. Carle ,
G.A. Pawloski  and
J.A. Rard
A.F.B. Tompson
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
C.J. Bruton
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
W.L. Bourcier
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
D.E. Shumaker
Affiliation:
Center for Applied Scientific ComputingLivermore, California, 94551
A.B. Kersting
Affiliation:
Analytical and Nuclear Sciences Division, Lawrence Livermore National Laboratory, Livermore, California, 94551
D.K. Smith
Affiliation:
Analytical and Nuclear Sciences Division, Lawrence Livermore National Laboratory, Livermore, California, 94551
S.F. Carle
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
G.A. Pawloski
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
J.A. Rard
Affiliation:
Geosciences and Environmental Technologies DivisionLivermore, California, 94551afbt@llnl.gov
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Abstract

Reactive transport simulations are being used to evaluate the nature and extent of radionuclide contamination within alluvium surrounding an underground nuclear test at the Nevada Test Site (NTS). Simulations are focused on determining the abundance and chemical nature of radionuclides that are introduced into groundwater, as well as the rate and extent of radionuclide migration and reaction in groundwater surrounding the working point of the test. Transport simulations based upon a streamline-based numerical model are used to illustrate the nature of radionuclide elution out of the near-field environment and illustrate the conceptual modeling process. The numerical approach allowed for relatively complex flow and chemical reactions to be considered in a computationally efficient manner. The results are particularly sensitive to the rate of melt glass dissolution, distribution of reactive minerals in the alluvium, and overall groundwater flow configuration. They provide a rational basis from which defensible migration assessments can proceed.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 608: Symposium QQ – Scientific Basis for Nuclear Waste Management XXIII , 1999 , 199
Copyright
Copyright © Materials Research Society 2000

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References

REFERENCES

1 U.S. DOE, Regional groundwater flow and tritium transport modeling and risk assessment of the underground test area, Nevada Test Site, Nevada, U. S. Department of Energy, Nevada Operations Office, Environmental Restoration Division, Las Vegas, NV, DOE/NV–477 (1997).Google Scholar
2 IAEA, The radiological situation at the atolls of Mururoa and Fangataufa. Inventory of radionuclides underground at the atolls. Interim version, Vol. 3, International Atomic Energy Agency, Vienna (1998).Google Scholar
3 Borg, I., Stone, R., Levy, H. B., and Ramspott, L. D., Information pertinent to the migration of radionuclides in ground water at the Nevada Test Site. Part 1: Review and analysis of existing information, Lawrence Livermore National Laboratory, Livermore, CA, UCRL-52078 (1976).Google Scholar
4 Germain, L. S. and Kahn, J. S., Phenomenology and containment of underground nuclear explosions, Lawrence Livermore National Laboratory, Livermore, CA, UCRL-50482 (1968 ).Google Scholar
5 Smith, D. K., Characterization of nuclear explosive melt debris, Radiochimica Acta, 69, 157–167 (1995).Google Scholar
6 Tompson, A. F. B., Bruton, C. J., and Pawloski, G. A., eds., Evaluation of the hydrologic source term from underground nuclear tests in Frenchman Flat at the Nevada Test Site: The Cambric test, Lawrence Livermore National Laboratory, Livermore, CA, UCRL-ID-132300 (1999), (http://www-ep.es.llnl.gov/www-ep/UGTA. August 2, 1999).Google Scholar
7 Hoffman, D. C., Stone, R., and Dudley, W. W. Jr, Radioactivity in the underground environment of the Cambric nuclear explosion at the Nevada Test Site, Los Alamos National Laboratory, Los Alamos, NM, LA-6877-MS (1977).Google Scholar
8 Bryant, E. A., The Cambric migration experiment: A summary report, Los Alamos National Laboratory, Los Alamos, NM, LA-12335-MS (1992).Google Scholar
9 Schwartz, L., Piwinskii, A., Ryerson, F., Tewes, H., and Beiringer, W., Glass from underground nuclear explosions. Journal of Noncrystalline Solids, 67, 559–591 (1984).Google Scholar
10 Mazer, J. J., Kinetics of glass dissolution as afunction of temperature, glass composition, and solution pH, Ph.D. thesis, Northwestern University (1987).Google Scholar
11 Baxter, R. G., Description of defense waste processing facility reference waste form and container, Savannah River, Aiken, SC, DP-1606, rev. 1 (1983).Google Scholar
12 Thiele, M. R., Batycky, R. P., Blunt, M. J., and Orr, F. M., Simulating flow in heterogeneous systems using streamtubes and streamlines, SPE Reservoir Engineering, 10, 5–12 (1996).Google Scholar
13 Yabusaki, S. B., Steefel, C. I., and Wood, B. D., Multidimensional, multicomponent, subsurface reactive transport in nonuniform velocity fields: code verification using an advective reactive streamtube technique, Journal of Contaminant Hydrology, 30, 299–331 (1998).Google Scholar
14 Steefel, C. I. and Yabusaki, S. B., OS3D/GIMRT, Software for modeling multicomponent and multidimensional reactive transport, User manual and programmer's guide, Version 1.0, Pacific Northwest National Laboratory, Richland, WA, PNL- 11166 (1996).Google Scholar