A thermal hydraulic design of the MTR-10 MW using the MTRTHA program

Abstract

In this research work, The MTRTHA code has been used to calculate all Thermal Hydraulic parameters (power density, Average heat flux, coolant velocity, Critical velocity, Pressure drop across channel, fuel, clad and coolant temperature distribution, …. .etc) for the IAEA MTR 10 MW research reactor, For the purpose of verifying the reliability of the software in the calculation of the MTR-type reactor.

The results of this work show a good agreement with International published results, as average heat flux calculated value was (21.36) W/cm² with relative difference smaller than (%0.83), while the coolant velocity value was (8.3) m/s and Critical velocity value was (10.938) m/s with relative difference smaller than (%0.01).The peak temperature for fuel, clad surface and coolant was 93^oC, 80^oC and 50^oC, respectively, while the pressure drop of the coolant through the reactor core was (0.194) bar with relative difference less than (%2.5).