System for reducing temperature of material leaked from containment of nuclear power plant and radionuclide content therein

Abstract

The invention belongs to the technical field of nuclear safety control, and relates to a system for reducing the temperature of a material leaked from a containment of a nuclear power plant and radionuclide content therein. The system comprises a pressure relief pipeline, a pressure relief pipeline heat exchanger, a filtering water tank, a filtering water tank heat exchanger, a filtering circuit and a gas returning pipeline, wherein one end of the pressure relief pipeline is connected with the pressure relief valve of the containment, the other end is connected with the filtering water tank, and the middle of the filtering water tank is connected with the pressure relief pipeline heat exchanger; the pressure relief pipeline heat exchanger is used for reducing the temperature of a leaked material derived from the pressure relief pipeline; the filtering water tank is used for filtering the radionuclide of a fission product carried in the leaked material through the filtering circuit arranged inside or outside the filtering water tank, and used for reducing the temperature of water contained therein through the filtering water tank heat exchanger arranged inside or outside the filtering water tank; and one end of the gas returning pipeline is connected with the gas outlet of the filtering water tank, and the other end is connected with the containment. By utilizing the system provided by the invention, the temperature of the material leaked from the containment of the nuclear power plant can be reduced, and the discharge of the radionuclide therein can be greatly reduced and even be completely eradicated.

Description

technical field [0001] The invention belongs to the technical field of nuclear safety control, and relates to a system for reducing the temperature of leakage material and the content of radionuclides in the containment of a nuclear power plant. Background technique [0002] In response to severe accidents, nuclear power plants of different reactor types have different preventive and mitigation measures to ensure the safety and reliability of nuclear power plants, as well as the radiation safety of plant staff and the public outside the site. If the primary circuit system of the reactor is in a continuous high-pressure state after the accident, when the lower head of the pressure vessel melts through, the molten material may be sprayed from the lower head of the pressure vessel into the reactor cavity, resulting in high-pressure molten pile injection. Subsequent spraying of saturated water, steam, and hydrogen may leave the reactor cavity with core fragments and reach differ...

AI Technical Summary

Problems solved by technology

However, the radionuclides dealt with by this measure have been released into the atmosphere of the containment vessel, and environmental releases (including but not limited to noble gases) will inevitably occur.

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