Hostname: page-component-586b7cd67f-dlnhk Total loading time: 0 Render date: 2024-11-25T17:42:55.142Z Has data issue: false hasContentIssue false
  • English
  • Français

Engineered Components for Spent Fuel Radioactive Waste Isolation Systems—are They Technically Justified?

Published online by Cambridge University Press:  15 February 2011

H. C. Burkholder
H. C. Burkholder*
Affiliation:
Battelle Memorial InstituteOffice of Nuclear Waste Isolation Columbus, Ohio
Get access

Extract

In response to draft radioactive waste disposal standards, R&D programs have been initiated in the United States which are aimed at developing and ultimately using radionuclide transport-delaying (e.g., long-lived waste containers) and radionuclide transport-controlling (e.g., very low release rate waste forms) engineered components as part of the isolation system. Before these programs proceed significantly, it seems prudent to evaluate the technical justification for development and use of sophisticated engineered components in radioactive waste isolation.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 11: Symposium – Scientific Basis for Nuclear Waste Management V , 1981 , 619
Copyright
Copyright © Materials Research Society 1982

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. U.S. Nuclear Regulatory Commission. (1981) 10 CFR 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories. Federal Register, 46 FR 35280. Office of Federal Register, Washington, D.C.Google Scholar
2. Klement, A. W. et al. . (1972) Estimates of Ionizing Radiation Doses in the United States 1960–2000. ORB/CSD 72–1. U.S. Environmental Protection Agency, Washington, D.C.Google Scholar
3. U. S. Department of Energy. (1980) Final Environmental Impact Statement-- Management of Commercially Generated Radioactive Waste. DOE/EIS- 0046F. Washington, D.C.Google Scholar
4. Burkholder, H. C. (1982) Engineered Components for Radioactive Waste Isolation Systems-Are They Technically Justified? ONWI-286.Google Scholar
4a Battelle Project Management Division, Office of Nuclear Waste Isolation, Columbus, Ohio.Google Scholar
5. Cloninger, et al. . (1980) An Analysis on the Use of Engineered Barriers for Geologic Isolation of Spent Fuel in a Reference Salt Site Repository. PNL-3356. Pacific Northwest Laboratory, Richland, Washington.CrossRefGoogle Scholar
6. Little, A. D., Inc. (1980) Technical Support of Standards for High-Level Radioactive Waste Management. EPA-520/4–79–007D. U.S. Environmental Protection Agency, Washington, D.C.Google Scholar
7. Harwell, M. A. et al. . (1981) Reference Site Initial Assessment for a Salt Dome Repository. PNL-2955. Pacific Northwest Laboratory, Richland, Washington.Google Scholar
8. Claiborne, H. C. and Gera, F. (1974) Potential Containment Failure Mechanisms and Their Consequences at a Radioactive Waste Repository in Bedded Salt in New Mexico. ORNL-TM-4639. Oak Ridge National Laboratory, Oak Ridge, Tennessee.Google Scholar
9. Girardi, F. et al. . (1977) Long-Term Risk Assessment of Radioactive Waste Disposal in Geological Formations. EUR 5902.e. Commission of European Communities, Ispra, Italy.Google Scholar
10. Logan, S. E. and Berbano, M. C. (1978) Development and Application of a Risk Assessment Method for Radioactive Waste Management. EPA 520/6–78– 005. U.S. Environmental Protection Agency, Washington, D.C.Google Scholar
11. Campbell, J. E. et al. . (1978) Risk Methodology for Geologic Disposal of Radioactive Waste: Interim Report. SAND-78–0029. Sandia Laboratories, Albuquerque, New Mexico.Google Scholar
12. Berman, L. E. et al. . (1978) Analysis of Some Nuclear Waste Management Options. UCRL-13917. The Analytic Sciences Corporation, Reading, Massachusetts.Google Scholar
13. Bingham, F. W. and Barr, G. E. (1979) Scenarios for Long-Term Release of Radionuclides from a Nuclear Waste Repository in the Los Medanos Region of New Mexico. SAND-78–1730. Sandia Laboratories, Albuquerque, New Mexico.Google Scholar
14. U. S. Department of Energy. (1979) Draft Environmental Impact Statement Waste Isolation Pilot Plant. DOE/EIS-0026-D. Washington, D.C.Google Scholar
15. Raymond, J. R. et al. . (1980) Test Case Release Consequence Analyses for a Spent Fuel Repository in Bedded Salt. PNL-2782. Pacific Northwest Laboratory, Richland, Washington.Google Scholar
16. International Fuel Cycle Evaluation Working Group 7. (1980) Release Consequence Analysis for a Hypothetical Geologic Radioactive Waste Repository in Salt. INFCE/DEP/WG7/16. International Atomic Energy Agency, Vienna, Austria.Google Scholar
17. Burkholder, H. C. (1981) The Development of Release Scenarios for Geologic Nuclear Waste Repositories—Where Have We Been?—Where Should We Be Going? Radionuclide Release Scenarios for Geologic Repositories, OECD Nuclear Energy Agency, Paris, France.Google Scholar
18. Cloninger, M. O. and Cole, C. R. (1981) An Analysis on the Use of Engineered Barriers for Isolation of Spent Fuel in Three Reference Geologies. PNL-3530. Pacific Northwest Laboratory, Richland, Washington.Google Scholar
19. Dove, F. H. et al. . Reference Site Initial Assessment for a Basalt Repository. PNL-3632. Pacific Northwest Laboratory, Richland, Washington.Google Scholar
20. Nuclear Fuel Safety Group. (1978) Handling of Spent Nuclear Fuel and Final Storage of Vitrified High-Level Reprocessing Wastes. Karn-Bransle Sakerhet, Stockholm, Sweden.Google Scholar
21. Nuclear Fuel Safety Group. Handling and Final Storage of Unreprocessed Spent Nuclear Fuel. Karn-Bransle-Sakerhet, Stockholm, Sweden.Google Scholar
22. International Fuel Cycle Evaluation Working Group 7. (1980) Release Consequence Analysis for a Hypothetical Geologic Radioactive Repository in Hard Rock. International Atomic Energy Agency, Vienna, Austria.Google Scholar
23. Lyon, R. B. (1980) Environmental and Safety Assessment for Nuclear Waste Disposal—The Canadian Approach. Waste Management 81 Symposium, University of Arizona, Tucson, Arizona.Google Scholar
24. Cloninger, M. O. and Sneider, S. C. (1982) Sensitivity of Spent Fuel Repository Performance Assessment to Variation in Radionuclide Retardation Coefficients. PNL-4296. Battelle Memorial Institute, Pacific Northwest Laboratory, Richland, Washington.Google Scholar
25. Burkholder, H. C. et al. (1976) “Incentives for Partitioning High- Level Waste. Nuclear Technology, 31, 202.Google Scholar
26. Hill, M. D. (1980) The Effect of Variations in Parameter Values on the Predicted Radiological Consequences of Geologic Disposal of High-Level Waste.Google Scholar
26a Scientific Basis for Nuclear Waste Management, 2, 753.Google Scholar
27. Sutcliffe, W. G. et al. . (1981) Uncertainties and Sensitivities in the Performance of Geologic Nuclear Waste Isolation Systems. ONWI-352. University of California, Lawrence Livermore National Laboratory, Livermore, California.Google Scholar