|dc.description||Thesis (M.Ing. (Nuclear Engineering))--North-West University, Potchefstroom Campus, 2007||
|dc.description.abstract||This study introduces a new method for the validation of the point kinetic neutronic model of
the PBMR. In this study the diffusion equation solution, as implemented in the TlNTE
PBMR 268 MW reactor model, replaces the point kinetic model, as implemented in the
Flownex V502 PBMR plant model. An indirect coupling method is devised and implemented
in an external program called Flownex-Tinte-Interface (FTI) to facilitate the data exchange
between these two codes.
The validation study of FTI indicates that the indirect coupling method introduces small
errors in data transfer between the two codes and therefore FTI is not suitable for very fast
thermal hydraulic and detailed reactor simulations. However, it is accurate enough for the
point kinetic validation study.
The comparison between transient simulation results shows that the point kinetic parameters
as implemented in V502 do not model the PBMR 268 MW correctly. Changes to some of the
point kinetic parameters produced results that are more acceptable. The results also reveal
that Flownex disregards any neutronic calculations after an explicit power change.
Further studies on the newest PMBR 400 MW reactor should determine if the point kinetic
parameters used are valid under all transient conditions. Thought must also be given into a
low-level integration of TINTE and Flownex. This could solve the problem of the induced
errors by the coupling method, but would increase computational time dramatically.||
|dc.title||Validation of the point kinetic neutronic model of the PBMR||en