The development of horizontally oriented prismatic micronuclear reactors is progressing rapidly, with deployment anticipated within the next decade. A thorough understanding of gas flow behavior during natural circulation is crucial for ensuring reactor safety and preventing accidents. To investigate this phenomenon, a dual-channel plenum-to-plenum facility (P2PF), designed as a simplified model of the reactor core, was experimentally studied under natural circulation conditions. Advanced measurement techniques, including thermocouples, microfoil sensors, and thermal gas flow sensors, were employed to capture critical thermal-hydraulic parameters such as helium temperature profiles, local heat transfer coefficients, and flow velocities across various heating intensities.
Zeitoun et al. (Wed,) studied this question.