Initial Results From Dissolution Testing of Spent Fuel Under Acidic Conditions

Conference · Wed Dec 01 00:00:00 EST 2004

OSTI ID:15011283

Hanson, Brady D; Friese, Judah I; Soderquist, Chuck Z

Flow through dissolution tests using leachants with pH in the range 2 to 7 have been conducted on a moderate burnup Light Water Reactor spent fuel. Such low pH conditions have been modeled as possibly occurring in a failed waste package at the proposed repository at Yucca Mountain. The release of total uranium, 99Tc, 90Sr, 137Cs, and 239&240Pu were measured for up to 90% total reaction of the specimens. The reaction rates, determine both from the cumulative release and the release normalized to surface area, were found to decrease with increasing pH and with increasing extent of reaction. The implications to instantaneous release and long-term behavior in a geologic repository are discussed.

• Research Organization: Pacific Northwest National Lab., Richland, WA (US)
• Sponsoring Organization: US Department of Energy (US)
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 15011283
• Report Number(s): PNNL-SA-42262; 830403000; TRN: US0501001
• Resource Relation: Conference: Scientific Basis for Nuclear Waste Management XXVIII, Conference location not supplied, Conference dates not supplied; Other Information: PBD: 1 Dec 2004
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
BURNUP
DISSOLUTION
MANAGEMENT
RADIOACTIVE WASTES
REACTION KINETICS
SPENT FUELS
SURFACE AREA
TESTING
URANIUM
WASTES
WATER
YUCCA MOUNTAIN
SPENT FUEL