Reactor pressure vessel experimental simulation body for pressurized water reactor water loss accident

Abstract

The invention discloses a reactor pressure vessel experimental simulation body for a pressurized water reactor water loss accident. The reactor pressure vessel experimental simulation body comprises areactor pressure vessel simulation body mass and a reactor core detection apparatus, wherein the reactor pressure vessel experimental simulation body mass comprises a pressure vessel simulation bodyand a bracketplant simulation body located in an inner cavity of the pressure vessel simulation body, the bracketplant simulation body is provided with a reactor core assembly simulation body inside,the pressure vessel simulation body comprises an upper end enclosure, a middle cylindrical barrel and a lower end enclosure, the reactor core assembly simulation body comprises a casing pipe and an electric heating element, the top of the casing pipe is a closed end, the bottom of the casing pipe is an open end, the bottom of the casing pipe extends downwardly and extends out of the lower end enclosure, and a data acquisition end of the reactor core detection apparatus is inserted into the casing pipe from the open end of the casing pipe. By adopting the reactor pressure vessel experimental simulation body for the pressurized water reactor water loss accident, the sealing performance between the reactor pressure vessel barrel and the reactor core can be prevented from being influenced by an acquisition route of the detection apparatus of the reactor core assembly simulation body.

Description

technical field [0001] The invention relates to the field of nuclear power, in particular to a reactor pressure vessel experiment simulation body used for pressurized water reactor loss of water accidents. Background technique [0002] A loss of water accident refers to an accident in which a breach or rupture occurs at the pressure boundary of the reactor's main circuit, and part or most of the coolant leaks. The loss of water accident is a key research content in nuclear reactor safety. As one of the design basis accidents of nuclear power plants, the accident has a relatively high probability of occurrence and involves complex thermal-hydraulic phenomena, such as critical flow at the breach and core liquid level collapse. The cooling effect of the core is reduced; the core may even be exposed, and the core is in the process of insufficient cooling, resulting in an increase in the temperature of the fuel cladding, which affects the thermal safety of the core. After the lo...

AI Technical Summary

Problems solved by technology

[0006] The purpose of the present invention is to provide a reactor pressure vessel experimental simulation body for a pressurized water reactor loss of water accident, to solve the need to carry out high temperature and high pressure sealing on the reactor pressure

Images