Waste/Rock Interactions Technology Program. Status report on LWR spent-fuel leach tests
Spent fuels with burnups of 9000, 28,000 and 54,500 MWd/MTU have been leach tested at 25/sup 0/C. Three leach-test procedures (Paige, IAEA and static) were used. IAEA and static tests were conducted in five different solutions: deionized water, sodium bicarbonate, sodium chloride, calcium chloride and Waste Isolation Pilot Plant B brine solutions. Elemental leach data are reported based on the release of /sup 90/Sr/sup +90/Y, /sup 106/Ru, /sup 137/Cs, /sup 144/Ce, /sup 154/Eu, /sup 239 +240/Pu, /sup 125/Sb, /sup 244/Cm, /sup 129/I, /sup 99/Tc, and total uranium. This is the first report on /sup 129/I and /sup 99/Tc from spent fuel. Termination of the Paige test showed that the plateout (radionuclide adsorption) on the test apparatus had negligible effect on the leach rate of cesium and plutonium, but a major (up to a factor of 50 times) effect on the curium leach rate. Three-hundred additional days of leach testing by the IAEA procedure, from 467 to 769 d, showed a continuation of the leaching trends observed during the first 467 d. Results from the first two static leach test series, 2 and 8 d, gave the /sup 129/I and /sup 99/Tc release numbers.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6921126
- Report Number(s):
- PNL-3473; TRN: 81-000065
- Country of Publication:
- United States
- Language:
- English
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SPENT FUELS
FISSION PRODUCT RELEASE
LEACHING
WATER COOLED REACTORS
FUEL CYCLE
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ANTIMONY 125
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CALCIUM CHLORIDES
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PLUTONIUM 239
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