Passive residual heat removal system for reactor

Abstract

The invention discloses a passive residual heat removal system for a reactor. The passive residual heat removal system comprises a water cooling pipe, a pressure vessel, an air cooler, a regulating valve and a chimney, the water cooling pipe is wound on the outer wall of the pressure container, an outlet of the water cooling pipe is communicated with an inlet of the adjusting valve through the air cooler, an outlet of the adjusting valve is communicated with an inlet of the water cooling pipe, the air cooler is located in the chimney, and an inlet air valve set is installed at an inlet in the bottom of the chimney. The heat exchange efficiency of the system is high, and the service life of the pressure vessel cavity concrete can be prolonged.

Description

technical field [0001] The invention belongs to the field of reactor passive waste heat derivation, and relates to a reactor passive waste heat discharge system. Background technique [0002] The current third and fourth generation advanced reactors require a safety-level passive waste heat removal system, which is used to conduct waste heat removal without relying on active equipment in an emergency state, thereby improving the failure safety of the reactor. [0003] The safety level passive waste heat removal system adopted by the pressurized water reactor is to draw the coolant from the heat pipe section of the primary circuit for cooling and then return to the heat pipe section of the primary circuit. Since the passive waste heat removal system of the PWR is connected to the primary circuit, the pressure of the primary circuit of the PWR generally exceeds 15MPa, and the heat transfer tube requires a high pressure rating, and the material needs to be made of special mater...

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Problems solved by technology

Although this passive waste heat removal system avoids the high cost of the PWR waste heat removal system and the risk of LOCA in the primary circuit, the outer surface of the pressure vessel is generally about 250 degrees Celsius, and the heat transfer efficiency of radiation and natural convection is too low, which affects the core. Waste heat export capability; the radiation heat transfer method will form a high temperature environment above 150°C in the pressure vessel chamber, and the long-term high temperature will cause the high-temperature aging of the concrete in the pressure vessel chamber and affect the life of the concrete

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