Pressure vessel external cooling system for floating nuclear power station

Abstract

The invention discloses a pressure vessel external cooling system for a floating nuclear power station, which belongs to the technical field of nuclear reactor engineering, and comprises a containment, a pressure vessel, a liquid gallium collection box, a heat pipe, a cooling cabin and a gallium storage box, the containment is arranged in a sea environment and is provided with a containing cavity; the pressure vessel and the liquid gallium collection box are arranged up and down and are positioned in the containing cavity of the containment; one end of the heat pipe is inserted into the liquid gallium collection box, and the other end of the heat pipe is arranged outside the liquid gallium collection box; the gallium storage box is positioned in the containing cavity of the containment; the gallium storage box is communicated with the liquid gallium collection box through a liquid gallium release valve; the cooling cabin is arranged at the lower end of the containment and located below the sea level of the sea environment. The system does not face the risk of cooling failure outside the reactor vessel caused by loss of the hot trap, does not generate a large amount of steam in the containment, avoids the problems of flow channel blockage and containment overpressure, and has the advantages of safety, stability and long-term operation.

Description

technical field [0001] The invention belongs to the technical field of nuclear reactor engineering, and in particular relates to an external cooling system for a pressure vessel of a floating nuclear power plant, which adopts liquid gallium as an intermediate heat transfer medium and heat pipes to transfer heat. Background technique [0002] Floating nuclear power plants can be used for power generation, seawater desalination, and can meet special needs such as regional power supply, offshore oil exploration, and isolated islands. Improving the safety of floating nuclear power plants (or reducing assumed serious accidents) is the key to the design of floating nuclear power plants. Intra-reactor retention (IVR) is one of the key strategies for mitigating presumed severe accidents in many advanced reactor designs. The success of IVR relies heavily on the external reactor vessel cooling (ERVC) through which decay heat is removed from the molten core in the lower head of the rea...

AI Technical Summary

Problems solved by technology

This leads to three defects in traditional ERVC: (1) A large amount of steam is generated in the flow channel, and the outlet of the flow channel is blocked, and the heat flux at the equator of the lower head exceeds the critical heat flux limit, which in turn causes the risk of molten material melting through the pressure vessel

(2) A large amount of steam is generated in the containment vessel, which may cause overpressure of the containment vessel and threaten the integrity of the containment vessel

(3) The traditional ERVC cannot run for a long time, because the pit water keeps heating up. When the temperature is high enough, the traditional ERVC will lose its cooling capacity

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