Initial Evaluation of the Effect of Neutron Absorbers on the Corrosion of Uranium-Aluminum Alloys
Aluminum-based spent nuclear fuel from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Monitored Geologic Repository. The melt-dilute treatment technology has been developed to consolidate fuel assemblies by a melting/casting process in which depleted uranium is added to reduce enrichment below 20 percent 235U. The melt-dilute product is essentially a binary uranium-aluminum alloy to which neutron absorber materials may be readily added. Demonstration of the compatibility and effectiveness of neutron-absorbing additions to the uranium-aluminum alloy, relative to criticality control, has been performed. The corrosion of uranium-aluminum alloys including neutron absorbers is being investigated in accordance with ASTM C1431-99. Testing includes vapor, static, single-pass flow, and electrochemical tests on surrogates of the melt-dilute treatment product. Exposure of uranium-aluminum alloys, including absorbers, to water vapor shows low post-passivation corrosion rates, similar to that of aluminum. The corrosion degradation sequences in the aqueous and vapor testing are assessed.
- Research Organization:
- Savannah River Site (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 773121
- Report Number(s):
- WSRC-MS-2000-00861
- Country of Publication:
- United States
- Language:
- English
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