The release of actinides, cesium, strontium, technetium, and iodine from spent fuel under unsaturated conditions

Conference · Sun Dec 31 00:00:00 EST 1995

OSTI ID:204213

Finn, P A; Hoh, J C; Wolf, S F ^[1]

---

1. and others

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, {sup 137}Cs, {sup 90}Sr, {sup 99}Tc, and {sup 129}I 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.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 204213
• Report Number(s): ANL/CMT/CP-85620; CONF-950946-9; ON: DE96006642; TRN: 96:008715
• Resource Relation: Conference: 5. international conference on the chemistry and migration behaviour of actinides and fission products in the geosphere, Saint-Malo (France), 10-15 Sep 1995; Other Information: PBD: 1995
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
YUCCA MOUNTAIN
SITE CHARACTERIZATION
UNDERGROUND FACILITIES
SPENT FUELS
UNDERGROUND DISPOSAL
HIGH-LEVEL RADIOACTIVE WASTES
WATER
RADIONUCLIDE MIGRATION
ACTINIDES