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Behavior of Carbon-14 in Waste Packages for Spent Fuel in a Repository in Tuff

Published online by Cambridge University Press:  26 February 2011

R. A. Van Konynenburg ,
C. F. Smith ,
H. W. Culham  and
C. H. Otto Jr.
R. A. Van Konynenburg
Affiliation:
Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94550
C. F. Smith
Affiliation:
Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94550
H. W. Culham
Affiliation:
Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94550
C. H. Otto Jr.
Affiliation:
Lawrence Livermore National Laboratory, P.O. Box 808, Livermore, CA 94550
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Abstract

Analysis of gas from a heated air-filled canister containing a spent fuel assembly before and after rupture of a fuel rod shows that about 1.5 mCi of 14C from the external surface of the assembly was rapidly oxidized and released as 14CO2 in excess oxygen at 275°C and 104rad/hr. After rupture, an additional 0.3 mCi was released, probably also from the external surface. The total 14C inventory in the entire 15×15 rod assembly including structural hardware is estimated to be 690 mCi. These measurements indicate that account will have to be taken of the time distribution of lifetimes of the canisters, and a broad definition of the “engineered system” may be necessary, in order to meet 1OCFR60 requirements with spent fuel in a repository in tuff.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 44: Symposium N – Scientific Basis for Nuclear Waste Management VIII , 1984 , 405
Copyright
Copyright © Materials Research Society 1985

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References

1. Nuclear Regulatory Commission, Proposed Rule 10 CFR Part 60, “Disposal of High-Level Radioactive Wastes in the Unsaturated Zone,” Federal Register, Vol.49, No. 33, pp. 5934–7 (Feb. 16, 1984).Google Scholar
2. Nuclear Regulatory Commission, Federal Regulation 10 CFR Part 60, “Disposal of High-Level Radioactive Wastes in Geologic Repositories,” (U. S. Government Printing Office, Washington, D.C. 1984).Google Scholar
3. Environmental Protection Agency, Proposed Rule 40 CFR Part 191,“Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes,” Federal Register, Vol. 47, No. 250 (Dec. 29, 1982) as modified to Working Draft No. 4 (April 17, 1984).Google Scholar
4. Braun, H., Gutowski, H., Bonka, H., and Grundler, D., “Plant for Retention of 14C in Reprocessing Plants for LWR Fuel Elements,” Proceedings of the 17th DOE Nuclear Air Cleaning Conference, Denver, August 2–5, 1982, edited by First, M.W. (U.S. Dept. of Energy, CONF-820833, Washington, D.C., 1983), p. 381.Google Scholar
5. Bush, R. P., “Carbon-14 Waste Management: A Review,” Proceedings of an International Conference on Radioactive Waste Management, Seattle, May 16–20, 1983 (International Atomic Energy Agency, Vienna, 1984), Vol. 2, p. 441.Google Scholar
6. Croff, A. G. and Alexander, C. W., “Decay Characteristics of Once-Through LWR and LMFBR Spent Fuels, High-Level Wastes, and Fuel-Assembly Structural Material Wastes,” ORNL/TM-7431 (Oak Ridge National Laboratory, Oak Ridge, Tennessee, 1980).CrossRefGoogle Scholar
7. Davis, W. Jr., “Carbon-14 Production in Nuclear Reactors,” ORNL/NUREG/TM-12 (Oak Ridge National Laboratory, Oak Ridge, Tennessee, 1977).Google Scholar
8. Crow, W. T., “Nitrogen Content of Light Water Reactor Fuel,” Nuclear Regulatory Commission, note to L. C. Rouse, Docket File 50–332 (Oct. 4, 1974), as cited in Ref. 7.Google Scholar
9. United Nations Scientific Committee on the Effects of Atomic Radiation, Ionizing Radiation: Sources and BiologicaZ Effects (United Nations, New York, 1982).Google Scholar
10. Unterzuber, R., Milnes, R. D., Marinkovich, B. A., and Kubancsek, G. M., “Spent Fuel Dry Storage Testing at E-MAD (March 1978 through March 1982),” PNL-4533, AESD-TME-3162 (Westinghouse Electric Corp, Advanced Energy Systems Division, Pittsburgh, PA, September, 1982).Google Scholar
11. Davis, R. B., “Data Report for the Nondestructive Examination of Turkey Point Spent Fuel Assemblies B02, B03, B17, B41 and B43,” HEDL-TME 79-68, (Hanford Engineering Development Laboratory, Richland, Washington, 1980).Google Scholar
12. Dobbins, J. C., “Histories of Spent Nuclear Fuel Assemblies While at the E-MAD Facility–December 1978 Through September 1982,” DOE/NV/10250-6 (Westinghouse Electric Corp., Mercury, Nevada, 1983).Google Scholar
13. Johnson, A. B. Jr. and Gilbert, E. R., “Technical Basis for Storage of Zircaloy-Clad Spent Fuel in Inert Gases,” PNL-4835 (Pacific Northwest Laboratory, Richland, Washington, 1983).CrossRefGoogle Scholar
14. Jones, A. R., Radiation Research 10, 655 (1959).CrossRefGoogle Scholar
15. Davis, R. B. and Pasupathi, V., “Data Summary Report for the Destructive Examination of Rods G7, G9, J8, I9, and H6 from Turkey Point Fuel Assembly B17,” HEDL-TME 80-85, (Hanford Engineering Development Laboratory, Richland, WA, 1981).Google Scholar
16. Lind, S. C., Hochanadel, C. J., and Ghormley, J. A., Radiation Chemistry of Gases (Reinhold, New York, 1961).Google Scholar
17. Croff, A. G., Bjerke, M. A., Morrison, G. W., and Petrie, L. M., “Revised Uranium-Plutonium Cycle PWR and BWR Models for the ORIGEN Computer Code,” ORNL/TM-6051 (Oak Ridge National Laboratory, Oak Ridge, TN, 1978).Google Scholar
18. International Atomic Energy Agency, Directory of Nuclear Reactors, Vol. X (International Atomic Energy Agency, Vienna, 1976), p. 201.Google Scholar
19. Brown, R. A., Christian, J. D., Thomas, T. R., Croff, A. G., and Jubin, R. T., “Recovery and Storage Policy Decisions for Airborne Radionuclides,” Proc. of an Int'l. Conf. on Radioactive Waste Management, Seattle, May 16–20, 1983 (International Atomic Energy Agency, Vienna, 1984), Vol. 2, p. 421.Google Scholar
20. Atkin, S. D., “Destructive Examination of 3-Cycle LWR Fuel Rods from Turkey Point Unit 3 for the Climax Spent Fuel Test,” HEDL-TME 80-89 (Hanford Engineering Development Laboratory, Richland, WA, 1981).Google Scholar
21. Einziger, R. E. and Fish, R. L., “Characterization of LWR Spent-Fuela Rods Used in the NRC Low-Temperature Whole Rod and Crud Performance Test,” NUREG/CR-2871, HEDL-TME 82-27 (Hartford Engineering Development Laboratory, Richland, WA, 1982).Google Scholar
22. Barner, J. O., “Characterization of LWR Spent Fuel MCC-Approved Testing Material ATM-101,” PNL-5109 (Pacific Northwest Laboratory, Richland, WA, 1984).Google Scholar