|Mtsetfwa, Sebenele Mugu
|Thesis (M.Sc. Engineering Sciences (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2012.
|This work develops a one dimensional, slab geometry, multigroup collision probability code named
Oklo which solves both criticality calculations and fixed source problems. The code uses the classical
collision probabilities approach where the first flight collision probabilities are calculated analytically for
void, reflected and periodic boundary conditions.
The code has been verified against analytical criticality benchmark test sets from Los Alamos National
Laboratory, which have been used to verify MCNP amongst other codes. The results from the code
show a good agreement with the benchmark test sets for the critical systems presented in this report.
The results from the code also match the infinite multiplication factors k and average scalar flux
ratios for infinite multiplicative systems from the benchmark test sets.
The criticality results and the fixed source results from the Oklo code have been compared with
criticality results and fixed source results from a discrete ordinates code and the results for both types
of problems show a good agreement with the results from the discrete ordinates code as we increase
the N for the discreet ordinates code.
|Integral transport equation
|Flat flux approximation
|A one–dimensional multi–group collision probability code for neutron transport analysis and criticality calculations