Type-IV out-of-core melt retention device after nuclear power station accidents

Abstract

The invention relates to a Type-IV out-of-core melt retention device after nuclear power station accidents, which comprises an inner wall, a steam channel wall with an opening on the bottom, a pressure container, an outer wall, a reactor core melt retention device and a guide plate, wherein the steam channel wall is fixed on the inner side of the inner wall, the pressure container is arranged in the steam channel wall, the outer wall is arranged around the outside of the inner wall, the reactor core melt retention device is fixed on the bottom of the inner wall, and the guide plate keeps a certain clearance with the inner wall and the reactor core melt retention device; a coolant descending channel is formed between the outer wall and the guide plate, the bottom of the guide plate is provided with a coolant inlet, and a coolant channel is arranged between the inner wall and the reactor core melt retention device; the reactor core melt retention device is provided with a reactor core melt retention groove, and the lower surface of the reactor core melt retention device is arched; and the reactor core melt retention device is prepared from an inorganic non-metallic refractory material. By adopting the out-of-core melt retention design, the melt is contained by different materials, and the structure of the coolant loop and guide plate is used for cooling the melt, thereby enhancing the safety of the nuclear power station.

Description

technical field [0001] The invention relates to an IV-type out-of-core smelt retention device after a nuclear power plant accident, in particular to an IV-type out-of-core smelt retention device after a nuclear power plant accident, which adopts a complete passive cooling design of the core to improve the safety of the nuclear power plant. Background technique [0002] Melt retention technology is an important mitigation measure for serious accidents in nuclear power, which can effectively solve the radioactive release and maintain the integrity of the safety boundary. At present, the third-generation nuclear power plants have adopted the mitigation measures for serious accidents after the pressure vessel is damaged. [0003] AP-1000 adopts passive measures for preventing and mitigating serious accidents, mainly including setting up molten core retention facility (IVR). The space between the outer wall of the vessel and the thermal insulation layer of the reactor pit is use...

AI Technical Summary

Problems solved by technology

It is worth noting that once the core melt melts through the pressure vessel, the IVR will be powerless

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