TRANSPORT AND DIFFUSION OF FISSION PRODUCTS IN GRAPHITE

Journal Article · Mon Dec 31 23:00:00 EST 1962 · Progr. Nucl. Energy

OSTI ID:4073526

Bromley, J

The processes involved in the diffusion and migration of fission products in graphites that are used as both can and moderator, e.g., dispersion fuel elements, in hightemperature reactors are discussed. The chemical state of the fission products, the paths followed by the fission products in fuel-graphite systems, the theory of the diffusion processes, and some experimental data on fission product migration in graphite are considered. 98 references. (R.E.U.)

• Research Organization: Atomic Energy Research Establishment, Harwell, Berks,
• NSA Number: NSA-18-009628
• OSTI ID: 4073526
• Journal Information: Progr. Nucl. Energy, Journal Name: Progr. Nucl. Energy Vol. Vol: Ser. IV, 5
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

BIBLIOGRAPHY
CANNING
CHEMICAL REACTIONS
CONTAMINATION
COOLANT LOOPS
DIFFUSION
DISPERSIONS
EQUATIONS
FISSION PRODUCTS
FUEL ELEMENTS
FUELS
GRAPHITE
GRAPHITE MODERATOR
HIGH TEMPERATURE
MEASURED VALUES
POROSITY
POWER PLANTS
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
THERMAL DIFFUSION
THERMODYNAMICS
TRANSPORT