Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database

<table class="table-group" id="tab4"><tr><td><table class="table"><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr class="thead"><td align="left">Quantity</td><td align="center">Range</td></tr><tr><td class="thead-hr" colspan="2"><hr/></td></tr><tr><td align="left">Pressure</td><td align="center">4.9–16.6 MPa</td></tr><tr><td align="left">Mass velocity</td><td align="center">550–4150 kg/m<sup>2</sup>s</td></tr><tr><td align="left">Inlet coolant temperature</td><td align="center">140–345°C</td></tr><tr class="table-tr"><td colspan="2"><hr class="tbody-hr"/></td></tr></table></td></tr></table>

Range of NUPEC PWR test facility operating conditions.

Science and Technology of Nuclear Installations

tab4

Table 4

Table 4: Comparative Analysis of CTF and Trace Thermal-Hydraulic Codes Using OECD/NRC PSBT Benchmark Void Distribution Database 