Thermal design parameters for a cylindrical fuel pin (Section 3.4)
Consider the PWR reactor of Example 3.1.
1. Evaluate the average neutron flux if the enrichment of the fuel is
3.25 wt%.
2. Evaluate the average volumetric heat generation rate in the fuel in
MW/m3. Assume that the fuel density is 90% of theoretical density.
3. Calculate the average linear power of the fuel, assuming there
are 264 fuel rods per assembly. Assume the fuel rod length to be
3658 mm.
Table 3.13
Summary of Energy Sources of Example 3.7
Sources Energy (GJ) Fraction (%)
1. Primary coolant 324.8 11.1
2. Secondary coolant 82.7 2.8
3. Decay heat (1 day) 2241.0 76.3
4. Chemical reaction 118.0 4.0
– Zr and H2O 36.3 1.2
– Zr and CO2 95.4 3.3
5. Combustion 37.3 1.3
– H2 combustion
– CO combustion
Total 2935.5 100.0
4. Calculate the average heat flux at the cladding outer radius, when the
cladding diameter is 9.5 mm.