An approach to the coupled dynamics of small lead cooled fast reactors

다국어 초록 (Multilingual Abstract)

A lumped kinetic modeling platform is developed to investigate the coupled nuclear/thermo-fluid featuresof the closed natural circulation loop in a low power lead cooled fast reactor. This coolant materialserves a reliable choice with noticeable thermo-physical safety characteristics in terms of natural convection.
Boussienesq approximation is resorted to appropriately reduce the governing partial differentialequations (PDEs) for the fluid flow into a set of ordinary differential equations (ODEs). As a maincontributing step, the coolant circulation speed is accordingly correlated to the loop operational powerand temperature levels. Further temporal analysis and control synthesis activities may thus be carriedout within a more consistent state space framework. Nyquist stability criterion is thereafter employed tocarry out a sensitivity analysis for the system stability at various power and heat sink temperature levelsand results confirm a widely stable natural circulation loop.

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