Hostname: page-component-848d4c4894-8bljj Total loading time: 0 Render date: 2024-06-29T01:36:56.495Z Has data issue: false hasContentIssue false
  • English
  • Français

Source-Term Analysis for Hanford Low-Activity Tank Waste Using the Reaction-Transport Code AREST-CT

Published online by Cambridge University Press:  03 September 2012

Y. Chen ,
B. P. McGrail  and
D. W. Engel
Y. Chen
Affiliation:
Pacific Northwest National Laboratory, PO Box 999, K6–81, Richland, WA, 99352, USA.
B. P. McGrail
Affiliation:
Pacific Northwest National Laboratory, PO Box 999, K6–81, Richland, WA, 99352, USA.
D. W. Engel
Affiliation:
Pacific Northwest National Laboratory, PO Box 999, K6–81, Richland, WA, 99352, USA.
Get access

Abstract

A general, integrated performance assessment code, AREST-CT, was used to analyze the influence of various factors on the release rates of radionuclides from a proposed facility for disposal of low-activity tank wastes. The code couples various process models together based on the framework of reaction-transport theory. The disposal facility was modeled as a 1-D column surrounded by soil. A borosilicate waste glass, LD6–5412 was the waste form considered in the analysis. Included in the simulations were 38 aqueous species, 14 minerals, 21 equilibrium reactions, and 16 kinetic reactions. Dissolution rate of the glass and the release rates of Te, Pu, U, Np, I, Se under different conditions were calculated for 50,000 years. The simulations revealed that 1) open exchange between the atmosphere and pore-water within the vault significantly improves the performance; 2) an ion-exchange reaction between the glass and aqueous phase increases the release rates significantly; and 3) at the hydrogeologie conditions under consideration, variation of the pore-water velocity has little effect on the release rate of radionuclides. These results provide a scientific basis for formulation of waste forms and engineering design of the disposal facility. Reaction-transport modeling can provide information on the long-term performance of disposal systems that are not obtainable from laboratory experiments alone or by conventional decoupled process models.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 465: Symposium II – Scienfific Basis for Nuclear Waste Management XX , 1996 , 1051
Copyright
Copyright © Materials Research Society 1997

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

REFERENCES

1. McGrail, B.P., and Engel, D.W., in Scientific Basis for Nuclear Waste Management XVI, edited by Interrante, C.G. and Pabalan, R.T. (Mater. Res. Soc. Proc. 294, Pittsburgh, PA, 1993) pp. 215–224.Google Scholar
2. McGrail, B.P., Steefel, C.I., Fort, J.A., Engel, D.W., Yabusaki, S.B., in Scientific Basis for Nuclear Waste Management XVIII, edited by Murakami, T. and Ewing, R. C., (Mater. Res. Soc. Proc. 353, Pittsburgh, PA, 1995) pp. 551–557.Google Scholar
3. Chen, Y., McGrail, B.P., and Engel, D.W., in Proceedings of International Conference on Deep Geological Disposal of Radioactive Waste, edited by Ohta, M.M. and Nuttall, K., (Can. Nucl. Soc.) September 16–19, 1996, Winnipeg, Manitoba, Canada.Google Scholar
4. Chen, Y., McGrail, B.P., and Engel, D.W., The Development of a General, Coupled Reaction-Transport Code: AREST-CT (in preparation).Google Scholar
5. Chen, Y., Chen, W., Park, A., Mu, J., and Ortoleva, P., A General, Coupled Model for Solute Transport and Reactions and Porous Medium Alteration (in preparation)Google Scholar
6. Lichtner, P.C., Principles and Practice of Reactive Transport Modeling, in Scientific Basis for Nuclear Waste Management XVIII, edited by Murakami, T. and Ewing, R. C., (Mater. Res. Soc. Proc. 353, Pittsburgh, PA, 1995) pp. 117–130.Google Scholar
7. Steefel, C.I. and Lasaga, A.C., A Coupled Model for Transport of Multiple Chemical Species and Kinetic Precipitation/Dissolution Reactions with Application to Reactive Flow in Single Phase Hydrothermal Systems, American Journal of Science, Vol. 294, 1994, pp529–592.10.2475/ajs.294.5.529Google Scholar
8. Chen, Y., Engel, D.W., McGrail, B.P., and Lessor, K.S., Report No. PNL-10692, Pacific Northwest Laboratory, Richland, Washington, USA, 1995.Google Scholar
9. Wolery, T.J., Report No. UCRL-MA-110662 PT III, Lawrence Livermore National Laboratory, Livermore, California, USA, 1992.Google Scholar
10. Kline, N.W., Report No. WHC-SD-WM-RPT-189, Westinghouse Hanford Company, Richland, Washington, USA, 1995.Google Scholar
11. Serne, R.J., Conca, J.L., LeGore, V.L., Cantrell, K.J., Lindenmeier, C.W., Campbell, J.A., Amonette, J.E., and Wood, M.I., Report No. PNL-8889 Vol. 1, Pacific Northwest Laboratory, Richland, Washington, USA, 1993.Google Scholar
12. McGrail, B.P., Ebert, W.L., Babel, A.J., and Peeler, D.K., Measurement of Kinetic Rate Law Parameters on a Na-Ca-Al Borosilicate Glass for Low-Activity Waste, submitted to J. Nuc. Mat., 1996.Google Scholar
13. Schmittroth, F.A., Report No. WHC-SD-WM-RPT-164, Westinghouse Hanford Company, Richland, Washington, USA, 1995.Google Scholar