Modeling of UO{sub 2} aqueous dissolution over a wide range of conditions

Conference · Mon Nov 01 04:00:00 EST 1993

OSTI ID:10149780

Steward, S A; Weed, H C

Previously it was not possible to predict reliably the rate at which spent fuel would react with groundwater because of conflicting data in the literature. The dissolution of the UO{sub 2} spent fuel matrix is a necessary step for aqueous release of radioactive fission products. Statistical experimental design was used to plan a set of UO{sub 2} dissolution experiments to examine systematically the effects of temperature (25--75C), dissolved oxygen (0.002--0.2 atm overpressure), pH (8--10) and carbonate (2-200{times}10{sup {minus}4} molar) concentrations on UO{sub 2} dissolution. The average uranium dissolution rate was 4.3 mg/m{sub 2}/day. The regression fit of the data indicate an Arrhenius type activation energy of 8750 cal/mol and a half-power dependence on dissolved oxygen in the simulated groundwater.

• 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: 10149780
• Report Number(s): UCRL-JC--114118; CONF-931108--102; ON: DE94011615
• Country of Publication: United States
• Language: English

Related Subjects

050700
052002
053000
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CARBONATES
DISSOLUTION
ENVIRONMENTAL ASPECTS
FUELS PRODUCTION AND PROPERTIES
GROUND WATER
HIGH-LEVEL RADIOACTIVE WASTES
LEACHING
OXYGEN
RADIOACTIVE WASTE DISPOSAL
SIMULATION
SOLVENT PROPERTIES
SPENT FUELS
UNDERGROUND DISPOSAL
URANIUM DIOXIDE
WASTE DISPOSAL AND STORAGE