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Finn, P.A.; Hoh, J.C.; Wolf, S.F.
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1995
Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States)1995
AbstractAbstract
[en] Drip tests to measure radionuclide release from spent nuclear fuel are being performed at 90 degrees C at a drip rate of 0.75 mL/3.5 days; the test conditions are designed to simulate the behavior of spent fuel under the unsaturated and oxidizing conditions expected in the potential repository at Yucca Mountain. This paper presents measurements of the actinide, 137Cs, 90Sr, 99Tc, and 129I contents in the leachates after 581 days of testing at 90 degrees C. These values provide an estimate of the source term for the long-lived radionuclide release under these test conditions. Comparisons are made between our results and those of other researchers
Original Title
Yucca Mountain Project
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1995; 14 p; 5. international conference on the chemistry and migration behaviour of actinides and fission products in the geosphere; Saint-Malo (France); 10-15 Sep 1995; CONF-950946--9; CONTRACT W-31109-ENG-38; Also available from OSTI as DE96006642; NTIS; US Govt. Printing Office Dep
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Report
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Conference
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