Uranium diffusion in H-451 graphite
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:5096930
The transport or diffusion of uranium (as a standin for plutonium) was investigated under conditions approximating those of the primary coolant loop in a high-temperature gas-cooled reactor. Profiles were obtained for uranium penetration in H-451 graphite at temperatures ranging from 900 to 1400/sup 0/C. Profile data for given temperatures were considered in terms of the following expression: (erf/sup -1/(1-C/C /SUB o/ ))/sup 2/=X/sup 2//4Dt, where C is the concentration of uranium at time t, for distance x, into the pellet; C /SUB o/ is a constant representing the uranium concentration at x = 0 for all t, and D is the diffusion coefficient. Diffusion coefficients for uranium initially present as dicarbide at 1000 and 1400/sup 0/C were found to be defined by Duc/sub 2/ = 3.5 X 10/sup -3/ exp(-4.8 X 10/sup 4//RT) cm/sup 2//s. For uranium initially present as dioxide at 900, 1000, and 1400/sup 0/C, diffusion coefficients are defined by Duo/sub 2/ = 2.34 X 10/sup -6/ exp(-3.2 X 10/sup 4//RT) cm/sup 2//s, where R is the gas constant and T is the temperature in degrees Kelvin.
- Research Organization:
- Oak Ridge National Laboratory, Chemical Technology Division, Oak Ridge, Tennessee
- OSTI ID:
- 5096930
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 68:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ACTINIDES
CALCULATION METHODS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
COOLING SYSTEMS
DIFFUSION
DIFFUSION LENGTH
DIMENSIONS
ELEMENTAL MINERALS
ELEMENTS
ENERGY SYSTEMS
GAS COOLED REACTORS
GAS PRODUCTION RATES
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
LENGTH
METALS
MINERALS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
TEMPERATURE DEPENDENCE
TRANSURANIUM ELEMENTS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTINIDE COMPOUNDS
ACTINIDES
CALCULATION METHODS
CARBIDES
CARBON
CARBON COMPOUNDS
CHALCOGENIDES
COOLING SYSTEMS
DIFFUSION
DIFFUSION LENGTH
DIMENSIONS
ELEMENTAL MINERALS
ELEMENTS
ENERGY SYSTEMS
GAS COOLED REACTORS
GAS PRODUCTION RATES
GRAPHITE
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
LENGTH
METALS
MINERALS
NONMETALS
OXIDES
OXYGEN COMPOUNDS
PLUTONIUM
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
TEMPERATURE DEPENDENCE
TRANSURANIUM ELEMENTS
URANIUM CARBIDES
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES