Hostname: page-component-848d4c4894-p2v8j Total loading time: 0.001 Render date: 2024-06-07T13:43:06.520Z Has data issue: false hasContentIssue false

Inventories of Iodine-129 and Cesium-137 in the Gaps and Grain Boundaries of LWR Spent Fuels

Published online by Cambridge University Press:  10 February 2011

W. J. Gray*
Affiliation:
Pacific Northwest National Laboratory, Richland, WA 99352, walt.gray@pnl.gov
Get access

Abstract

Performance assessment calculations that support geologic disposal of spent nuclear fuel in a potential repository at Yucca Mountain, Nevada, are based in part on the assumption that 2% of the total inventories of 135Cs, 129I, and 99Tc are located in the gap and grain-boundary regions where they could dissolve rapidly if the spent fuel were to be contacted by groundwater. Actual measured values reported here for a few light-water reactor (LWR) spent fuels show that the combined gap and grain-boundary inventories of 129I approximately equaled the fission-gas release fractions. For 137Cs, the combined gap and grain-boundary inventories were approximately one third of the fission-gas release fractions. These measured values can be used to replace the 2% estimate and thus reduce the uncertainties in the calculations.

Type
Research Article
Copyright
Copyright © Materials Research Society 1999

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. Thomas, L.E. and Guenther, R.J. in So. Basis for Nucl. Waste Management XII, edited by Lutze, W. and Ewing, R.C. (Mater. Res. Soc. Proc. 127, Pittsburgh, PA, 1992) pp. 293300.Google Scholar
2. Civilian Radioactive Waste Management System, Management and Operating Contractor (CRWMS M&O), Viability Assessment, Technical Basis Document. Chapter 6, “Waste Form Degradation, Radionuclide Mobilization and Transport Through the Engineered Barrier System”. B000000C0-01717-4301-00006 Rev 00, Las Vegas, Nevada, Dec. 1998.Google Scholar
3. Gray, W.J., Strachan, D.M., and Wilson, C.N. in Sci. Basisfor Nicw. Waste Management XP, edited by Sombret, C.G. (Mater. Res. Soc. Proc. 257, Pittsburgh, PA, 1992) pp. 353360.Google Scholar
4. Gray, W.J. and Wilson, C.N.. Spent Fuel Dissolution Studies TY1991 to 1994. PNL-10540, Pacific Northwest Laboratory, Richland, Washington, 1995.Google Scholar
5. Stroes-Gascoyne, S., Moir, D.L., Kolar, M., Porth, R.J., McConnell, J.L. and Kerr, A.H. in Sci. Basis for Nucl. Waste Management XVIII, edited by Murakami, T. and Ewing, R.C. (Mater. Res. Soc. Proc. 353, Pittsburgh, PA, 1995) p. 625–63 I.Google Scholar
6. RI Guenther, Blahnik, D.E., Campbell, T.K., Jenquin, U.P., Mendel, JE., Thomas, L.E., and Thornhill, CK. Characterizationo f Spent Fuel Approved Testing Material- A IM-103. PNL-5109-103, Pacific Northwest Laboratory, Richland, Washington, 1988.Google Scholar
7. Guenther, R.J. Blahnik, D.E., Jenquin, U.P., Mendel, JE., Thomas, L.E., and Thornhill, C.K. Characterization of Spent Fuel Approved Testing Material – A IM-104. PNL-5109-104, Pacific Northwest Laboratory, Richland, Washington, 1991.Google Scholar
8. Guenther, R.J. Blahnik, D E., Campbell, T.K., Jenquin, U P., Mendel, J.E., Thomas, L.E, and Thornhill, C.K Characterization of Spent Fuel Approved Testing Material – A “V-I05. PNL-5109-105, Pacific Northwest Laboratory, Richland, Washington, 1991.Google Scholar
9. Guenther, R.J. Blahnik, D.E., Campbell, T.K., Jenquin, UP., Mendel, J.E., and Thornhill, C.K. Characterization of Spent Fuel Approved Testing Material – A TM-106. PNL-5109-106, Pacific Northwest Laboratory, Richland, Washington, 1988.Google Scholar
10. Stroes-Gascoyne, S., J. Nucl. Mater. 238, 264 (1996). 493Google Scholar
11. Thomas, L.E. and Chariot, L.A., Ceramic Transactions 9, 397 (1990).Google Scholar
12. Einziger, R.E., Thomas, L.E., Buchanan, H.C., and Stout, R.B., J. Nucl. Mater. 190, 53 (1992).Google Scholar
13. Gray, W. J. and Thomas, L.E., in High Level Radioactive Waste Management, Proceedings of the Third International Conference (American Nucl. Soc., La Grange Park, IL, 1992) pp. 14581464.Google Scholar
14. Taylor, P., Behnke, R., Bruneau, D. L., Nye, C. D., and Wood, D. D., A Second Examination of Fragments of Unirradiated and Irradiated CANDU Fuel, and Irradiated L WR Fuel, Oxidized in Air at 130°C and 170°Cfor Approximately One Thousand Days. EPRI Report In Press. Palo Alto, California 94304.Google Scholar