modelFuelThermalPower
Meshed model that describes the dynamic of the conduction of heat generated
by fission in a fuel rod.
Information
# Fuel Heat Transfer1
This module resolve the heat transfer equation in the fuel rod, based on the fuel properties, *cp* and "k",
computed in [FuelProperties](modelica://ThermoSysPro.NuclearCore.FuelProperties).
## Heat Transfer Resolution
The Finite Volumes approach is used, leading to the following equation for each node (axial thermal conduction is neglected):
$$Mnode*cp_{i,j}\frac{dT_{i,j}}{dt} = W_{i,j} + Wcond_{i,j}-Wcond_{i,j+1}$$
where the radial themal conduction term is:
$$Wcond_{i,j+1} = \frac{k_{i,j}+k_{i,j+1}}2 * \frac{T_{i,j}-T_{i,j+1}}{rvi_{j+1}-rvi_j} * S_{i,j}$$
and where *i* is the axial index, *j* the radial index, *T* the temperature in the node, *S* the radial surface between two nodes,
*Mnode* the mass in the node and *W* the power generated in the node.
It has to be noticed that the discretization is based on constant volumes, instead of constant radial steps;
*rsi* is the radial coordinate of the volumes boundary, *rvi* the radial coordinate of the volumes centers (centers in volumic terms).
## Doppler Effect
The effective temperature used for the Doppler effect can be computed, for each axial section, using the Rowlands weighting function [1]:
$$T_{i,eff} = \frac59T_{i,surface} + \frac49T_{i,center}$$
then, weighted axially as a function of the generated power:
$$T_{effg} = \frac{W_i}{W_T}*T_{i,eff} $$
To improve the the representativity of the *center* and *surface* temperatures, they are linearly extrapolated from the volume node temperature:
$$ T_{i,center} = T_{i,1}*1.5 - T_{i,2}*0.5 $$
$$ T_{i,surface} = T_{i,end}*1.5 - T_{i,end-1}*0.5 $$
The *linear* extrapolation is possible because of the constant volume discretization which give a linear solution under certains hypotheses
(constant and homogenoeus power, constant conductivity). Under the same assomptions, it is also possible to compare the results in with the analytical solution [2]:
$$ T_{i,center}-T_{i,surface}=\frac{W_i}{4\pi k} $$
and thus validate the extrapolation of the *center* and *surface* values.
## Gap Heat Trasfer
For the gap, the following thermal convection equation is used, where \\(h_{gap}\\) is a user defined constant:
$$ Wcond_{i,end} = h_{gap} * S_{i,end} * (T_{i,surface} - T_{i,clad}) $$
- [1]. G. Rowlands, *Resonance absorption and non-uniform temperature distributions*, Journal of Nuclear Energy, 1962.
- [2]. N.E. Todreas, M. S. Kazimi, Nuclear System I, Thermal Hydraulics Fundamentals. Taylor&Francis, 1798.
## Copyright © EDF 2002 - 2026
## ThermoSysPro Version 4.2Parameters
| Type | Name | Default | Description |
|---|---|---|---|
| Real[Nz] | zWt | {sin((i - 0.5)*Lseg*pi/Length)/Length for i in 1:Nz} | Axial distribution of the thermal power produced in the zone i of the fuel |
| Boolean | steady_state | true | |
| ThermoSysPro.Units.SI.Temperature | Tstart | 973.15 | |
| ThermoSysPro.Units.SI.CoefficientOfHeatTransfer | heat_coeff_gap | 10000 | Heat Tranfer Coefficient between the fuel rods and the internal wall of the cladding |
| Fuel Properties | |||
| Real | fuel_porosity | 0.05 | Fuel porosity |
| Real | oxy_on_metal | 2 | Oxyde on Metal Ratio |
| ThermoSysPro.Units.SI.Density | rho_uo2 | 10950 | Density of UO2 |
| Boolean | isMOX | false | Whether fuel is MOX or not |
| Real | pu_mFraction | 0 | PuO2 Mass Fraction |
| ThermoSysPro.Units.SI.Density | rho_puo2 | 11500 | Density of PuO2 |
| ThermoSysPro.Units.SI.Density | rho | (1 - fuel_porosity)*1/(pu_mFraction/rho_puo2 + (1 - pu_mFraction)/rho_uo2) | Density of MOX |
| Geometry | |||
| Integer | Rods_per_FA | 264 | Number of fuel Rods per Fuel Assembly |
| Integer | FA | 193 | Radius of the fuel pellet |
| ThermoSysPro.Units.SI.Radius | Rp | 0.004095 | Radius of the fuel pellet |
| ThermoSysPro.Units.SI.Radius | Rclad | 0.00418 | Internal radius of the cladding |
| Integer | Nz | 6 | Number of axial zones |
| Integer | Nr | 5 | Number of radial zones |
| ThermoSysPro.Units.SI.Length | Length | 4.270 | Active lenght of the fuel rods |
| ThermoSysPro.Units.SI.Radius[Nr] | rsi | {sqrt(i*Rp^2/Nr) for i in 1:Nr} | Radii of volume skins (constant volume) |
| ThermoSysPro.Units.SI.Radius[Nr] | rvi | {sqrt((i - 0.5)*Rp^2/Nr) for i in 1:Nr} | Radii of volume centers (constant volume) |
Connectors
| Type | Name | Default | Description |
|---|---|---|---|
| ThermoSysPro.Thermal.Connectors.ThermalPort[Nz] | C_clad | ||
| ThermoSysPro.InstrumentationAndControl.Connectors.InputReal | Wt_fuel | ||
| ThermoSysPro.InstrumentationAndControl.Connectors.OutputReal | Teff_fuel |
Components
| Type | Name | Default | Description |
|---|---|---|---|
| FuelProperties[Nz,Nr] | fuel | Fuel Properties | |
| ThermoSysPro.Units.SI.Temperature[Nz,Nr] | T | Temperature of the fuel | |
| ThermoSysPro.Units.SI.Temperature[Nz] | Tcenter | Temperature at the center of the fuel | |
| ThermoSysPro.Units.SI.Temperature[Nz] | Tout | Temperature of surface of the fuel | |
| ThermoSysPro.Units.SI.Temperature[Nz] | Teff | Effective temperature of the UO2 per zone, used for the calculation of the Doppler effect | |
| ThermoSysPro.Units.SI.Temperature | Teffg | Effective global temperature of the UO2, used for the calculation of the Doppler effect | |
| ThermoSysPro.Units.SI.Temperature[Nz] | Tg | Internal T of the cladding | |
| ThermoSysPro.Units.SI.Power | Wt | Total thermal power produced by the UO2 fuel | |
| ThermoSysPro.Units.SI.Power[Nz,Nr + 1] | Wcond | Thermal power exchanger between nodes by conduction | |
| ThermoSysPro.Units.SI.LinearPowerDensity[Nz] | linW | zWt_norm*Wt/Nrods/Length | Linear Power Density |