Development of a mathematical model for the dissolution of uranium dioxide. II. Statistical model for the dissolution of uranium dioxide tablets in nitric acid

Journal Article · Tue Mar 01 00:00:00 EST 1988 · Sov. Radiochem. (Engl. Transl.); (United States)

OSTI ID:6437409

Zhukovskii, Yu M; Luksha, O P; Nenarokomov, E A; Pronin, A V

We have derived a statistical model for the dissolution of uranium dioxide tablets for the 6 to 12 M concentration range and temperatures from 80/sup 0/C to the boiling point. The model differs qualitatively from the dissolution model for ground uranium dioxide. In the indicated range of experimental conditions, the mean-square deviation of the curves for the model from the experimental curves is not greater than 6%.

• OSTI ID: 6437409
• Journal Information: Sov. Radiochem. (Engl. Transl.); (United States), Vol. 29:4; Other Information: Translated from Radiokhimiya; 29: No. 4, 506-508(Jul-Aug 1987)
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
NITRIC ACID
SOLVENT PROPERTIES
NUCLEAR FUELS
PRODUCTION
URANIUM DIOXIDE
DISSOLUTION
STATISTICAL MODELS
AUTOMATION
CHEMICAL REACTION KINETICS
OPTIMIZATION
PARAMETRIC ANALYSIS
PROCESS CONTROL
SENSITIVITY ANALYSIS
SOLUBILITY
TEMPERATURE DEPENDENCE
ACTINIDE COMPOUNDS
CHALCOGENIDES
CONTROL
ENERGY SOURCES
FUELS
HYDROGEN COMPOUNDS
INORGANIC ACIDS
KINETICS
MATERIALS
MATHEMATICAL MODELS
OXIDES
OXYGEN COMPOUNDS
REACTION KINETICS
REACTOR MATERIALS
URANIUM COMPOUNDS
URANIUM OXIDES
050700* - Nuclear Fuels- Fuels Production & Properties
400201 - Chemical & Physicochemical Properties