Hostname: page-component-586b7cd67f-2brh9 Total loading time: 0 Render date: 2024-11-25T18:51:54.512Z Has data issue: false hasContentIssue false
  • English
  • Français

NWTS Waste Package Design and Materials Testing

Published online by Cambridge University Press:  21 February 2011

J. F. Kircher  and
D. J. Bradley
J. F. Kircher
Affiliation:
Battelle Memorial Institute, Office of Nuclear Waste Isolation, 505 King Avenue, Columbus, OH 43201
D. J. Bradley
Affiliation:
Battelle Pacific Northwest Laboratory, Richland, WA 99352
Get access

Extract

It is generally accepted that waste to be disposed of in a deep geologic repository will be suitably packaged. The design of such packages depends on the criteria which they must meet and the geochemical environment in which they are to be placed. Both the criteria and the environment must be considered in determining the components required to make up the package, the functions those components are to perform, and the materials of which the components are to be made.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 15: Symposium D – Scientific Basis for Nuclear Waste Management VI , 1982 , 383
Copyright
Copyright © Materials Research Society 1983

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. Engineered Waste Package Conceptual Design for Disposal in Salt, Draft, AESD-TIE-3131 (Nov. 1981).Google Scholar
2. Waste Package Concepts for Use in the Conceptual Design of the Nuclear Waste Repository in Basalt, Draft, AESD-TI3-3142 (July, 1982).Google Scholar
3. Conceptual Waste Package Designs for Disposal of Nuclear Waste in Tuff, Draft, AESD-TME-3138 (May, 1982).Google Scholar
4. Kuhn, W.L., et al, “Development of a Leach Model for a Commercial Nuclear Waste Glass”, PNL-SA-10359 (1982).Google Scholar
5. Moak, D.P., “Waste Package Materials Screening and Selection”, ONWI-312 (Oct. 1982).Google Scholar
6. Guidelines for the Development of Testing of NWTS Waste Package Materials, U.S. Department of Energy, NWTS-34 (July 1982).Google Scholar
7. Bradley, D.J., et al, “Integrated Materials Testing Report: Basalt and Tuff”, PNL-4452 (1982).Google Scholar
8. Moak, D.P., et al, “Waste Package Materials Testing for a Salt Repository” (in publication).Google Scholar
9. Molecke, M.A., et al, “Materials for High-Level Waste Canister/Overpacks in Salt Formations”, ANS Annual Meeting in Los Angeles, CA., (June 7–10, 1982) SAND82–0429J.Google Scholar
10. Westerman, R.E., et al, “Development of Structural Barriers for Containment of Nuclear Waste in Basalt”, ANS Annual Meeting, Los Angeles, CA., (June 7–10, 1982) PNL-SA-10145.Google Scholar
11. Westerman, R.E., et al, “Evaluation of Candidate Structural Barrier Materials for Containment of Nuclear Waste in Basalt and Tuff Repositories” PNL-4364 (1982).Google Scholar
12. Pitman, S.G., “Investigation of Susceptibility of Titanium Grade 2 and Titanium Grade 12 to Environmental Cracking in a Simulated Basalt Repository Environment”, PNL-3915 (Oct. 1981).Google Scholar
13. Buckwalter, C.Q., Pederson, L.R., and McVay, G.L., “The Effects of Surface Area to Solution Volume Ratio and Surface Roughness on Glass Leaching”. Accepted for publication in J. Non-Crystalline Solids. PNL-SA-9488 (1981).Google Scholar
14. Hench, L.L., “Physical Chemistry of Glass Surfaces”, J. of Non-Crystalline Solids, Vol. 25, p. 343 (1977).CrossRefGoogle Scholar
15. El Shamy, T.M., and Douglas, R.W., “Kinetics of the Reaction of Water with Glass”, Glass Technology, Vol. 13 (NO. 3) p. 77 (1972).Google Scholar
16. Bradley, D.J., et al, “Elemental Release from Glass and Spent Fuel”, ONWI-275 (Oct. 1981).Google Scholar
17. McVay, G.L., and Pederson, L.R., “Effect of Gamma Radiation on Glass Leaching”, J. American Ceramic Society, 64(3):154–158 (1981).Google Scholar
18. McVay, G.L., Weber, W.J., and Pederson, L.R., “Effects of Radiation on the Leaching Behavior of Nuclear Waste Forms”, Nuclear and Chemical Waste Management, 2:103–108, PNL-SA-8951 (1981).Google Scholar
19. McVay, G.L., and Buckwalter, C.Q., “The Effect of Iron on Waste Glass Leaching” submitted to the J. of the American Ceramic Society, PNL-SA-10474 (1982).Google Scholar
20. Ruppen, J.A., Diegle, R.B., Glass, R.S., and Headley, T.J., “Some Effects of Microstructure and Chemistry on Corrosion and Hydrogen Embrittlement of TiCode-12, Scientific Basis for Nuclear Waste Management-6, Brookins, D. Ed., Elsevier-North Holland, New York.Google Scholar
21. Nowak, E.J., “Radionuclide Sorption and Migration Studies of Getters for Backfill Barriers”, SAND-79-1110, July, 1980.Google Scholar
22. Nowak, E.J., “Diffusion of Radionuclides in Brine Saturated Backfill Barrier Materials”, Scientific Basis for Nuclear Waste Management-6, Brookins, D., Ed., Elsevier-North Holland, New York.Google Scholar