In this paper, we present a mathematical model for the simulation of transient neutronic and thermohydraulic behaviour of the PWR core and the primary circuit of a nuclear power plant. The point kinetics equations are used to model the core neutronics and the improved lumped parameter formulation proposed by Regis et al. (2000) and Su and Cotta (2001) is used to model the fuel dynamics. A two-region model is used for the pressurizer and for the primary-side of the steam generator. A pump model is implemented to obtain the flowrate variation during total or partial loss of flow. Several transient events and accidents are simulated and qualitatively agree with the results of more detailed engineering models.
- Nuclear Engineering Division
A Simplified Model for Dynamic Simulation of the Primary Circuit of Pressurized Water Reators
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Su, J, & Pontual, T. "A Simplified Model for Dynamic Simulation of the Primary Circuit of Pressurized Water Reators." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 465-473. ASME. https://doi.org/10.1115/ICONE12-49159
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