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Filtering by: Subject Nuclear fuels Decade 1990-1999 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