Nuclear power plant reactor pressure vessel and shield walling composite structure

Abstract

The present invention provides a nuclear power plant reactor pressure vessel and shielding wall composite structure comprising a reactor pit shielding wall, a reactor pit enclosed by the reactor pit shielding wall, a reactor pressure vessel arranged in the reactor pit, and a thermal insulation layer arranged outside the reactor pressure vessel, up-and-down-through flow channels are respectively arranged between the thermal insulation layer and the reactor pressure vessel, and the thermal insulation layer and the reactor pit shielding wall, the lower part of the reactor pit shielding wall is provided with a reactor pit water injection pipeline in the manner of penetration, an accommodation space is arranged on the inner wall of the upper part of the reactor pit shielding wall, a return flow path is arranged in the reactor pit shielding wall, and the return flow path is used for communicating the accommodation space and the reactor pit bottom space. Compared with the prior art, the return flow path is arranged in the reactor pit shielding wall to ensure saturated water entrained by steam can smoothly flow back into the reactor pit, so that a stable natural circulation can be formed between a rising flow path and the return flow path in the reactor pit to ensure the reactor pressure vessel can be continuedly and rapidly cooled under severe accident conditions.

Description

technical field [0001] The invention belongs to the field of dealing with severe accidents of nuclear power plants, and more specifically relates to a combined structure of reactor pressure vessels and shielding walls of nuclear power plants capable of handling severe accident conditions. Background technique [0002] Since the Chernobyl, Three Mile Island, and Fukushima nuclear power plant accidents, countries all over the world have paid unprecedented attention to nuclear power safety. While putting forward higher requirements for the probability of serious accidents in next-generation nuclear power plants, they have combined countries' Based on the characteristics of nuclear power units in service and under construction, an improvement plan for severe accident mitigation strategies is proposed. In the new version of the "Nuclear Power Plant Design Safety Regulations" (HAF102) and the IAEA guideline NS-G-1.10 issued by the China Nuclear Safety Administration on April 18, 2...

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Problems solved by technology

[0005] In some published nuclear power designs, the special structural design of the support ring of the reactor pressure vessel provides a natural circulation return flow channel for external cooling. High, unable to provide return flow path for out-of-heap cooling

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