Verification of the Point Lepreau SMOKIN Code with Plant Transient Data

Abstract

Recently a simulation model of the Point Lepreau reactor has been developed using the modal kinetic solutions incorporated in the SMOKIN computer code. This model utilizes 15 harmonic flux modes calculated/rom eigenvalue solutions of the two group diffusion equation. This model includes the capability to model most reactor physics and reactor control aspects of the plant. In order to verify the correct functioning of the model, simulations of past Point Lepreau plant transients were performed with the SMOKIN computer code. Comparisons we made with plant transient data taken from the Point Lepreau PAW data base. This verification process will ensure that future transient and impairment analysis can be performed reliably, and with confidence, within the verified bounds of the models fidelity. This paper describes these comparisons, the methodology of the verification, and the results.