3D view of one assembly of UCFR

For analysis of thermal hydraulic safety aspect, MATRA-LMR and SLTHEN code are used. MATRA-LMR (Multichannel Analyzer for steady-state and Transient in Rod Array for Liquid Metal Reactor) was developed as a subchannel analysis code to calculate the thermal-hydraulic characteristic of liquid metal reactors such as fuel, cladding, and coolant temperatures. With this code, the specific major parameters can be obtained and analyzed with other reactor to confirm the safety of the reactor.
SLTHEN (Steady-State LMR core Thermal-Hydraulic Analysis code based on Energy Model) is also analysis code which analyze the safety margin of the reactor. This code can evaluate the whole assemblies of nuclear core with considering peaking factor of each assembly and interaction with assemblies. In this lab, we used these codes to evaluate the concept of Ultra-long Cycle Fast Reactor (UCFR) which has been developed in UNIST.
In our lab, we design the secondary or third system which produces the electricity in nuclear power plant. Different types of turbine system (steam turbine, helium turbine, S-CO2 turbine) are studied and evaluated which could be the appropriate system for the new concept of reactor like UCFR. Using the software, we can optimize the system and get the good efficiency.

Example design of the third system of UCFR