nukapprentice said:
I was wondering if anyone has any actual data on the surface temperature of a fuel rod as a function of time. I am really curious as I am trying out a model I made using the fractional calculus. Or if anyone could point in the right direction to find said data that would be great as well.
BWR or PWR?
Unless one has a thermocouple on the surface, the temperature must be derived from validated models, and possibly with temperature measurements from core inlet and outlet thermocouples.
In a BWR, there is some subcooling at the inlet, but much of the coolant is at saturated conditions, but the local coolant condition may be subcooled, saturated liquid, saturated liquid with nucleate boiling or liquid+steam in bulk boiling.
In PWRs, the coolant inlet temperature varies (285 to 293°C) according to the particular reactor. The exit temperature may vary from 315 to 330°C depending on the rating of the fuel rod. The coolant mass flux can vary from about 3500 to 3800 kg/m
2-s.
The coolant surface temperature depends on the coolant temperature (which is a function of the coolant inlet temperature and enthalpy rise in the subchannel) and the heat transfer coefficient. Ideally, the coolant surface temperature is not much more than 340°C for long periods of time, in order to minimize the corrosion of the cladding. But predicted temperatures can be on the order of 345 to 347°C, with nucleate boiling, and this may promote crud (metal (Fe,Ni,Cr) oxide) formation, in addition to the oxidation of the cladding surface. A key issue in control of activation products is the control of crud through pH control in the primary system, and possibly the use of Zn-injection in the primary system.