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The Expected Environment for Waste Packages in a Salt Repository

Published online by Cambridge University Press:  25 February 2011

L. R. Pederson ,
D. E. Clark ,
F. N. Hodges ,
G. L. Mcvpy  and
D. Rai
L. R. Pederson
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA, 99352
D. E. Clark
Affiliation:
Battelle Memorial Institute, Office of Nuclear Waste Isolation, 505 King Avenue, Columbus, OH 43201
F. N. Hodges
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA, 99352
G. L. Mcvpy
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA, 99352
D. Rai
Affiliation:
Pacific Northwest Laboratory, P. O. Box 999, Richland, WA, 99352
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Abstract

This paper discusses results of recent efforts to define the very near-field (within approximately 2m) environmental conditions to which waste packages will be exposed in a salt repository. These conditions must be considered in the experimental design for waste package materials testing, which includes corrosion of barrier materials and leaching of waste forms. Site-specific brine compositions have been determined, and “standard” brine compositions have been selected for testing purposes. Actual brine compositions will vary depending on origin, temperature, irradiation history, and contact with irradiated rock salt. Results of irradiating rock salt, synthetic brines, rock salt/brine mixtures, and reactions of irradiated rock salt with brine solutions are reported.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 26: Symposium D – Scientific Basis for Nuclear Waste Management VII , 1983 , 417
Copyright
Copyright © Materials Research Society 1984

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References

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