Drain system for nuclear power plant

Abstract

A drain system for a shutdown cooling system of a pressurized water reactor type of a nuclear power plant (10) has an increased flow rate in the drain pipe (28) and drain pump (33). The hot leg (18) connected drain pipe has a vaned vortex breaker (30) mounted therein between its connection with the hot leg (18) lower region and the drain pump (32). This minimizes vortex-created cavitation in the drain pump thereby permitting the increased flow rate.

Description

technical field [0001] The invention relates to a high-efficiency drainage system suitable for the pressurized water shutdown cooling system of a nuclear power station. Specifically, the present invention can minimize the cavitation phenomenon caused by the coriolis effect (coriolis effect) vortex in the discharge pump of the shutdown cooling system, thereby increasing the flow rate of the cooling medium in the discharge system. Background technique [0002] In a pressurized water reactor (PWR) type nuclear power plant, the cooling medium fluid is essentially boron plus water, which is continuously transported through a closed loop between a nuclear reactor and one or more steam generators. [0003] During nuclear power production, the pressurized cooling medium absorbs the heat released by the thermonuclear reactions taking place in the reactor. The heated cooling medium then flows through a main pipe, aptly called the "heat leg" of the circulation loop. The heat pipe sup...

AI Technical Summary

Problems solved by technology

Such a vortex is undesirable as it limits the rate at which the cooling medium can be drained from the drain system and may eventually cause cavitation in the drain pump

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