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CHAPTER


                  Reactor thermal-

                  hydraulics                                        10







                  10.1 Introduction
                  Temperature and pressure of reactor fluids and solids are important variables in
                  steady state and transient operation. Along with associated coefficients of reactivity,
                  they determine the magnitude of reactivity feedbacks. Conservation of mass, energy,
                  and momentum are the basis for thermal-hydraulics models. However, since pressure
                  transients reach a new steady state so much faster in a transient than mass or energy,
                  the differential equation for momentum is usually unnecessary. Much of the infor-
                  mation in this chapter comes from Ref. [1].
                     This chapter includes short descriptions of major heat transport systems in
                  nuclear power reactors. Chapters 12, 13, and 14 provide more detailed information
                  about power reactor characteristics and control systems.



                  10.2 Heat conduction in fuel elements
                  Most of the reactors addressed in this book use cylindrical UO 2 fuel rods clad in zir-
                  caloy and have a gas-filled gap between the UO 2 and the cladding. Fuel heat transfer
                  in reactors with non-cylindrical fuel elements (such as high temperature gas cooled
                  reactors and molten salt reactors).is not addressed here.
                     A complete heat transfer model would require a partial differential equation in
                  two spatial dimensions (axial and radial … azimuthal is not required) and time. Solu-
                  tions of such a model equation are known, but they are not suitable for coupling with
                  models for cooling fluid. Instead, lumped parameter models (also, sometimes
                  referred to as nodal models) must be used. Lumped parameter models involve break-
                  ing the system into regions with uniform internal properties and coupling to adjacent
                  regions. It is possible to model fuel rods with concentric radial lumps, but the sim-
                  plest and most common lumped parameter model for cylindrical fuel elements uses a
                  single radial node.
                     Consider a single radial node model for a fuel element with heat transfer to fluid
                  coolant. The fuel has mass, M f , and specific heat capacity, C f . The model equation is
                  as follows:
                                            dT f
                                        M f C f  ¼ UA T f  θ avg + P f          (10.1)
                                             dt
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                  Dynamics and Control of Nuclear Reactors. https://doi.org/10.1016/B978-0-12-815261-4.00010-X
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