Improved lumped analysis of transient heat conduction in a nuclear fuel rod
作者： Clarissa R Regis , Renato M Cotta , Jian Su , None
DOI: 10.1016/S0735-1933(00)00116-0
关键词: Materials science 、 Boiling water reactor 、 Thermal conduction 、 Heat transfer coefficient 、 Mechanics 、 Heat flux 、 Heat transfer 、 Nuclear reactor 、 Transient (oscillation) 、 Thermal hydraulics 、 Thermodynamics
摘要: Transient heat conduction in a nuclear fuel rod is analysed by an improved lumped parameter approach. The circunferential symmetry assumed with the transfer through gap modelled coefficient. Hermite approximation for integration used to obtain average temperature and flux radial direction. Significant improvement over classical formulation has been achieved. proposed model can be stability analysis of BWR, simplified PWR or real-time simulator power plants.
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