CFD Simulation of Thermal‐Hydraulic Benchmark V1000CT‐2 Using ANSYS CFX
In: Science and technology of nuclear installations, Band 2009, Heft 1
ISSN: 1687-6083
Plant measured data from VVER‐1000 coolant mixing experiments were used within the OECD/NEA
and AER coupled code benchmarks for light water reactors to test and validate computational fluid
dynamic (CFD) codes. The task is to compare the various calculations with measured data, using
specified boundary conditions and core power distributions. The experiments, which are provided for
CFD validation, include single loop cooling down or heating‐up by disturbing the heat transfer in the
steam generator through the steam valves at low reactor power and with all main coolant pumps in
operation. CFD calculations have been performed using a numerical grid model of 4.7 million
tetrahedral elements. The Best Practice Guidelines in using CFD in nuclear reactor safety applications
has been used. Different advanced turbulence models were utilized in the numerical simulation. The
results show a clear sector formation of the affected loop at the downcomer, lower plenum and core
inlet, which corresponds to the measured values. The maximum local values of the relative temperature
rise in the calculation are in the same range of the experiment. Due to this result, it is now possible to
improve the mixing models which are usually used in system codes.