University of Birmingham > Talks@bham > Applied Mathematics Seminar Series > Coupled Thermal Hydraulics and Neutronics Analysis of Nuclear Reactors

Coupled Thermal Hydraulics and Neutronics Analysis of Nuclear Reactors

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If you have a question about this talk, please contact Dr Tom Montenegro-Johnson.

Historically, nuclear reactor analysis is divided into thermal hydraulic analysis that addresses the flow field and temperature distributions in fuel, cladding and coolant, and neutronic analysis that addresses the neutron flux distributions. External iterations are required to reach a converged design configuration of a nuclear reactor. In recent years, research efforts have focused on coupled thermal hydraulics and neutronics analysis of nuclear reactors to ensure a more realistic modeling and to reduce computational costs. This talk will addresses some approaches of coupled thermal hydraulics and neutronics analysis, including zero-dimensional reduced model, one-dimensional model coupled model, CFD with point kinetics model, CFD with Monte Carlo simulation, porous medium formulation with neutron diffusion equation, and internal coupling of specialized nuclear codes (COBRA-TF + PARCS ).

This talk is part of the Applied Mathematics Seminar Series series.

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