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Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-Level Radioactive Waste Disposal Containers in U.S.: A Critical Literature Review

Published online by Cambridge University Press:  26 February 2011

Joseph C. Farmer  and
R. Daniel McCright
Joseph C. Farmer
Affiliation:
University of California, Lawrence Livermore National Laboratory, Livermore, CA 94550
R. Daniel McCright
Affiliation:
University of California, Lawrence Livermore National Laboratory, Livermore, CA 94550
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Abstract

Three iron-based to nickel-based austenitic alloys and three copper-based alloys are being considered in the United States of America as candidate materials for the fabrication of high-level radioactive waste containers. The austenitic alloys are Types 304L and 316L stainless steels as well as the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper), CDA 613 (Cu-7A1), and CDA 715 (Cu-3ONi). Waste in the forms of spent fuel assemblies from reactors and borosilicate glass will be sent to a proposed repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and in gamma radiation.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 127: Symposium BERLIN – Scientific Basis for Nuclear Waste Management XII , 1988 , 359
Copyright
Copyright © Materials Research Society 1989

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References

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