Fast Reactor Transient Analysis Using the Generalized Quasi-Static Approximation

The numerical results that have been obtained for various reactor characteristics using the generalized quasi-static approximation for the study of fast reactor transients are analyzed. This approximation leads to a set of coupled nonlinear mixed boundary initial value problems for “amplitude” and “shape” neutron fluxes that are solved with a Newton-successive over-relaxation algorithm. Some details are given on the time integration module. Comparisons are established with the results obtained by other codes.