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

<div>Comparison of the temperature distribution in the hot channel of the CARR reactor between the COTENP code and reported results [<a href="/journals/stni/2018/9874196/#B7">7</a>]. TF is the centerline temperature, Tclad is the cladding temperature, and TC is the coolant temperature.</div>

Science and Technology of Nuclear Installations

fig9

Figure 9

Figure 9: Validation of the COTENP Code: A Steady-State Thermal-Hydraulic Analysis Code for Nuclear Reactors with Plate Type Fuel Assemblies 