The dissolution rate of UO{sub 2} in the alkaline regime under oxidizing conditions using a simplified ground water analog

Conference · Wed Jan 01 04:00:00 EST 1992

OSTI ID:10142308

Leider, H R; Nguyen, S N; Weed, H C; Steward, S A

The major factor controlling the long term release of radionuclides from spent fuel in a geologic repository is the leaching/dissolution by groundwater of the UO{sub 2} matrix, since more than 90% of the radionuclide waste is contained in the fuel matrix. The objective of this investigation is to provide experimental dissolution rates for UO{sub 2} samples which can be used to develop a mechanistic release model (or models) for UO{sub 2+x} (x{ge}0) under repository conditions. Several types of data will be obtained from this study: (1) the dissolution rates of UO{sub 2} as a function of pI-L temperature, carbonate and oxygen fugacity; (2) the comparison of the steady state dissolution rates of ``not-reduced`` versus ``reduced`` UO{sub 2} samples and of single crystal versus polycrystalline UO{sub 2} under identical experimental conditions; (3) the pre- and post-test surface analyses of the samples to provide information on the surface phases that may be formed under experimental conditions.

• Research Organization: Lawrence Livermore National Lab., CA (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 10142308
• Report Number(s): UCRL-JC--108815; CONF-920430--104; ON: DE93009314
• Country of Publication: United States
• Language: English

Related Subjects

052002
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ACID NEUTRALIZING CAPACITY
CHEMICAL REACTION KINETICS
DISSOLUTION
GLASS
GROUND WATER
LEACHING
MATHEMATICAL MODELS
OXIDATION
OXYGEN
PH VALUE
R CODES
RADIONUCLIDE MIGRATION
URANIUM OXIDES
WASTE DISPOSAL AND STORAGE