The study on optimization of overspeed test of steam-driven auxiliary water supply pump in nuclear power plant

The steam-driven auxiliary water supply pump, utilized within the Auxiliary Water Supply System (ASG) of nuclear power plants, is classified as nuclear safety level-3 and RCCM-2, marking it as a critical sensitive component and a specialized safety facility. This pump is pivotal, particularly when the main feedwater system fails, as it is designed to activate promptly and dissipate the residual heat from the reactor core, thereby directly influencing the safety of the unit. Periodic testing of this pump is crucial and significantly impacts the duration of the unit’s overhaul. Currently, a mechanical overspeed test is conduc ted in each fuel cycle to verify the pump’s overspeed protection function. The success rate of this test directly affects the overha ul period of the nuclear power plant. To enhance the reliability of the steam pump and minimize its impact on the safe operation of the unit, this paper explores the optimization of the mechanical overspeed test for the steam-driven auxiliary water supply pump.