Research and development on hydraulic characteristics of fuel assemblies
In addition to the role of safely and efficiently transferring the heat generated by uranium fission to the coolant, the fuel assembly assumes the role of safely shutting down the reactor by smoothly inserting the control rods. Therefore, during the improvement and development of fuel assemblies, in order to ensure that the fuel assemblies function as designed under hydraulic conditions simulating the internal environment of the reactor, the following characteristics are measured and evaluated using our Mitsubishi Fuel Research and Development Hydraulic Facility (MIRAI).
- Pressure loss of fuel assemblies
- Flow velocity distribution in fuel rod bundles
- Flow-induced vibration of fuel rods and fuel assemblies
- Insertability of control rods
Fuel assembly hydraulic test loop diagram
(MIRAI: Mitsubishi Fuel Research and Development Hydraulic Facility)