Continue Homework 7 and Homework 8. Read the TRACE Theory Manual Section on the conduction equation.
To prepare for this lecture you should read the ME 540 lecture on finite volume methods.
The last heat transfer lecture was about how codes like TRACE or RELAP5 model the transport of heat between metal and fluid. Today we need to extend the discussion to the conduction problem within the heat structure. I hope to show you that understanding and intellegently using these features can have a significant effect on the results.
When you think of heat conduction in a Nuclear Power plant, your natural inclination is to focus on the fuel rods. We will in fact do just that in this class. However, in an actual plant simulation, remember that a tremendous amount of energy is stored in all the heated metal of the system. Failure to account for this stored heat will generally result in significant errors in the prediction of accident scenarios. Accurate modeling of stored heat includes both conduction solutions for all metal mass, and adequate conduction mesh refinement near the interior surfaces of this metal. A conduction mesh that is too coarse near the surface contacting the fluid will significantly underestimate the temperature derivative (and hence heat flux) just inside the metal surface after a rapid change in fluid temperature.
Modeling of fuel rod conduction in TRACE is accomplished through the Heat Structure (HTSTR) component, using a fairly standard finite volume method. However, the calculation is complicated significantly by the presence of several materials within the rod ( oxide pellets, gas gap, and zirc cladding).
Given basic rod bundle geometry (rod pitch and diameter, and number
of rods) you
should be able to calculate the available area for axial fluid flow.
You should also be able to
calculate a hydraulic diameter based on wetted perimeter of the bundle.
You should also
learn the "secret" TRACE hydraulic diameter for best bundle heat
transfer (diagonal surface to
surface distance between rods in the bundle). This second method
is often more appropriate if you learn that data from heated tube
experiments rather than rod (or tube) bundle experiments has been used
for the heat transfer coefficients used in a bundle.
Although we won't cover any details you should also know that
transfer is not the only mechanism that must be considered.
Particularly, when dealing with
BWR cores or hot voided PWR cores, you will need to consider
contributions of infrared
radiation. This provides direct transport of heat from rods to liquid
drops, between rods with
different surface temperatures, and in BWRs transfer between the rod
surfaces and the
channel can wall. Understand that "view factors" give you a way to
calculate how much
radiation can be transported between specific portions of metal. They
are obtained by tracing
all possible light rays from one type surface to points on another
surface. The good news here is that in standard fuel bundle
configurations TRACE can compute the necessary view factors for
you. Take a graduate
course in radiation heat transport for details on methods for
calculating view factors.
It is important to understand the impact of your finite volume mesh
on the results of the simulation: