EBR-II blanket fuel leaching test using simulated J-13 well water.
A pulsed-flow leaching test is being conducted using three EBR-II blanket fuel segments. These samples are immersed in simulated J-13 well water. The samples are kept at a constant temperature of 90 C. Leachate is exchanged weekly and analyzed for various nuclides which are of interest from a mobility and longevity point of view. Our primary interest is in the longer-lived species such as {sup 99}Tc, {sup 237}Np, and {sup 241}Am. In addition, the behavior of U, Pu, {sup 90}Sr, and {sup 137}Cs are being analyzed. During the course of this experiment, an interesting observation has been made involving one of the samples which could indicate the possible rapid ''anoxic'' oxidation of uranium metal to UO{sub 2}.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10808
- Report Number(s):
- ANL/ED/CP-96471; TRN: US0103857
- Resource Relation:
- Conference: American Nuclear Society 3rd Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998; Other Information: PBD: 15 May 1998
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
EBR-2 REACTOR
SPENT FUELS
DISSOLUTION
GROUND WATER
LEACHATES
LEACHING
OXIDATION
URANIUM
RADIONUCLIDE MIGRATION
TECHNETIUM 99
NEPTUNIUM 237
AMERICIUM 241
PLUTONIUM
STRONTIUM 90
CESIUM 137
URANIUM DIOXIDE