Out-of-pile collection, split charging and retention system for reactor melts

Abstract

The invention discloses an out-of-pile collection, split charging and retention system for reactor melts. The system comprises a melt collection device, a multi-crucible dispersion and retention device and a cooling loop, wherein the melt collecting device is arranged on the vertical supporting inner wall of the pressure vessel and comprises an inclined face and a surrounding plate, and the surrounding plate is folded towards the center. The melt collecting device is of a two-layer structure and comprises a lower heat insulation layer and a surface lubricating layer. The multi-crucible dispersion retention device is arranged at the bottom of a reactor pit and comprises a central main crucible and a plurality of auxiliary crucibles, the central main crucible and the auxiliary crucible are connected through a pore passage penetrating piece; the opening of the central main crucible faces the opening of the coaming; and the cooling loop is connected with the reactor pit so as to cool the multi-crucible dispersion retention device in the reactor pit. The system has the beneficial effects that by adopting the design of melt collection and early-stage lubrication, the amount of the melt is concentrated, and the melt is controllably transferred; besides, the main crucible and the auxiliary crucible are communicated, so that split charging is effectively achieved, the heat exchange area is increased, and the cooling time is shortened.

Description

technical field [0001] The invention belongs to the field of nuclear industry, and in particular relates to a system for collecting, distributing and retaining reactor melt outside the reactor. Background technique [0002] At present, dozens of large-scale second-generation improved nuclear power plants are under construction and in operation in my country, but most of them have not been equipped with effective external melt retention systems. After the Fukushima accident in Japan, the safety of nuclear power plants, especially the prevention and mitigation of severe accidents, is more urgent. At present, under severe accidents, the cooling and retention strategies of the core melt can be mainly divided into two types: 1) The cooling and retention of the melt in the pressure vessel (IVR), this technology first appeared in the Loviisa VVER-440 power station in Finland , and have been applied in the design of AP600, AP1000, APR1400, CAP1400 (1400MWe pressurized water reactor...

AI Technical Summary

Problems solved by technology

At present, under severe accidents, the cooling and retention strategies of the core melt can be mainly divided into two types: 1) The cooling and retention of the melt in the pressure vessel (IVR), this technology first appeared in the Loviisa VVER-440 power station in Finland , and have been applied in the design of AP600, AP1000, APR1400, CAP1400 (1400MWe pressurized water reactor designed by State Nuclear Power Technology Co., Ltd.) and ACP1000 (1000MWe pressurized water reactor jointly developed and designed by China National Nuclear Corporation and China General Nuclear Power Group), Due to the controversial estimation of the heat flux density of the core melt loaded on the inner wall of the RPV, the current international mainstream opinion believes that the IVR technology is not suitable for larger power reactors, such as reactors above 1000MWe; 2) The melt outside the pressure vessel Cooling and Retention (EVR), which is used in the Russian-designed VVER-1000 model and the European Advanced Pressurized Water Reactor EPR model designed by the French ANP

Images