Thermal hydraulic analysis of advanced heavy water reactor

摘要

The Advanced Heavy Water Reactor (AHWR) adopts natural circulation core cooling during startup, power raising and accidental conditions in addition to the normal full power operating condition. The thermal hydraulic characteristics of such a natural circulation reactor depends on the geometry of system, pressure, inlet sub-cooling, radial and axial power distribution in the core. A computer code, THABANA-MOD2 is used for the thermal hydraulic analysis of AHWR. The effect of core height and diameter of tail pipe on the thermal margin and channel flow rate has been studied.