Neutronic and Thermalhydraulic Evaluation of Annular Fuel in PWR with Three Different Nanofluids

In pressurized nuclear reactors, one of the fuel design principles is centerline temperature limit. Since thermal conductivity UO2 not high, increases rapidly from surface to center. To overcome this limitation, use annular type fuels instead solid improvement efforts. study, effects using in a typical PWR are investigated. At same time, adding nanoparticles (〖Al〗_2 O_3,Cu and TiO_2) coolant water case also For both cases, neutronic thermalhydraulic calculations made compared. point view, it has been shown that does cause significant change k_eff value but presence reduces k_eff. This reduction maximum for Cu+water minimum 〖Al〗_2 O_3+water nanofluids. positively affects limits addition could provide an additional contribution this, provided very small amounts (φ