Corrosion mechanisms of spent fuel under oxidizing conditions
Conference
·
OSTI ID:542061
The release of {sup 99}Tc can be used as a reliable marker for the extent of spent oxide fuel reaction under unsaturated high-drip-rate conditions at 90{degrees}C. Evidence from leachate data and from scanning and transmission electron microscopy (SEM and TEM) examination of reacted fuel samples is presented for radionuclide release, potential reaction pathways, and the formation of alteration products. In the ATM-103 fuel, 0.03 of the total inventory of {sup 99}Tc is released in 3.7 years under unsaturated and oxidizing conditions. Two reaction pathways that have been identified from SEM are (1) through-grain dissolution with subsequent formation of uranyl alteration products, and (2) grain-boundary dissolution. The major alteration product identified by x-ray diffraction (XRD) and SEM, is Na-boltwoodite, Na[(UO{sub 2})(SiO{sub 3}OH)]{lg_bullet}H{sub 2}O, which is formed from sodium and silicon in the water leachant.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 542061
- Report Number(s):
- ANL/CMT/CP--93030; CONF-970902--; ON: DE98000644
- Country of Publication:
- United States
- Language:
- English
Similar Records
Corrosion mechanisms of spent fuel under oxidizing conditions
Spent fuel reaction - the behavior of the {epsilon}-phase over 3.1 years
Leaching patterns and secondary phase formation during unsaturated leaching of UO{sub 2} at 90{degrees}C
Conference
·
Mon Sep 01 00:00:00 EDT 1997
·
OSTI ID:653001
Spent fuel reaction - the behavior of the {epsilon}-phase over 3.1 years
Conference
·
Mon Dec 30 23:00:00 EST 1996
·
OSTI ID:477547
Leaching patterns and secondary phase formation during unsaturated leaching of UO{sub 2} at 90{degrees}C
Technical Report
·
Thu Oct 31 23:00:00 EST 1991
·
OSTI ID:140730