Device and method for measuring leak tightness of interlayer containment of nuclear power station

Abstract

The invention discloses a device for measuring the leak tightness of an interlayer containment of a nuclear power station. The device comprises a pressure regulating assembly, a data measuring assembly and a data acquiring and processing component, wherein the pressure regulating assembly is communicated with the interlayer containment; the data measuring assembly is distributed inside and outside the interlayer containment, and is used for measuring a plurality of measurement signals of the inside and outside of the interlayer containment under the different internal pressures of the interlayer containment and transmitting the plurality of measurement signals through different paths; the plurality of measurement signals comprise directly transmitted measurement signals and measurement signals to be converted; the data acquiring and processing component is connected with the data measuring assembly through different paths and is used for computing the plurality of directly transmitted measurement signals and converted measurement signals which are received after the pressure is changed for a plurality of times so as to obtain the measurement result of a leakage rate of the interlayer containment. The device, provided by the invention, for measuring the leak tightness of the interlayer containment of the nuclear power station establishes a computation model of the interlayer containment leakage rate and the uncertainty thereof and meets the standard requirement by means of reliable validation. Furthermore, the invention also discloses a method for measuring the leak tightness of the interlayer containment of the nuclear power station.

Description

technical field [0001] The invention relates to the technical field of pressure measurement, in particular to a device and method for measuring the airtightness of an interlayer containment vessel of a nuclear power plant in a negative pressure environment. Background technique [0002] The containment of third-generation nuclear power units is divided into an inner containment and an outer containment. The ring corridor between the inner containment and the outer containment is called the interlayer containment, which is responsible for the safety of containing radioactive materials under accident conditions. Features. In order to ensure that it can still maintain sufficient negative pressure during normal operation and accidents, verify its sealing before charging to ensure that it meets the design requirements. [0003] In the existing technology, the containment test is collectively referred to as the inner containment test in the third-generation units. The inner conta...

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Problems solved by technology

[0003] In the existing technology, the containment test is collectively referred to as the inner containment test in the third-generation units. The inner containment verification is the strength and sealing of the containment itself, that is, to limit the leakage of radioactive materials from the island to the outside under accident conditions. The interlayer containment only verifies the airtightness, that is, the ability of the interlayer containment to contain radioactive substances under accident conditions. At present, there is no independent test plan and system for the airtightness of the interlayer containment

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