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Filtering by: Subject Nuclear fuels Degree Name Master of Science (M.S.) Subject Fuel burnup (Nuclear engineering)

Monte Carlo burnup analysis code development and application to an incore thermionic space nuclear power system

Creator:

Abdul-hamid, Shahab A.

Abstract:

Lattice bum-up calculations in thermal reactors are complicated by the necessity for use of transport theory to represent fuel rods, control rods, and burnable absorbers, by many time-dependent variables which must be considered in the analysis, and by geometric complexity which introduces time-dependent, spatial-spectral variations. Representation of lattice structure in...

Resource Type:

Masters Thesis

Full Text:

theory is essential to accurately predict the nuclear reaction rates in the fuel rods, control rods, and