Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies

<div>Variation in the wall superheat temperature with heat flux for the proposed correlations.</div>

Science and Technology of Nuclear Installations

Figure 11: Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies 