The present study investigates distributions of pressure and temperature in the SMART, which is one of the nuclear reactors developed by KAERI. The pressure, the velocity, and the temperature are calculated under nominal operation and non-uniform temperature distributions are predicted in the inlet of core generated by the cases of broken-down steam generator. 3D-numerical simulations using a FVM commercial code is performed to calculate the distributions. Under nominal operation, the pressure drop is the highest in the steam generators as well as the temperature decrement is the highest. Broken-down steam generator yields the unmixed flow. When the steam generator related to the fourth floor in the flow mixing header assembly is broken down, the unmixed flow generates the narrowest hot flow region and the widest temperature range at the inlet of the reactor core.
Bibliographical noteFunding Information:
This work was supported by the Korea Atomic Energy Research Institute.
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering