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J. Devooght, E. H. Mund, B. Arien, A. Siebertz
Nuclear Science and Engineering | Volume 88 | Number 2 | October 1984 | Pages 191-199
Technical Note | doi.org/10.13182/NSE84-A28403
Articles are hosted by Taylor and Francis Online.
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.