Method for calculating pressure-bearing performance of nuclear containment vessel

Abstract

The invention relates to a method for calculating the pressure-bearing performance of a nuclear containment vessel, and the method specifically comprises the steps of obtaining the geometric dimension parameters of the nuclear containment vessel according to the drawing design data or measurement data, and building a material constitutive relation mathematical model of steel; based on the idea of equivalent simplification, simplifying the common steel bars and the prestressed tendons into thin steel shells, calculating the equivalent thickness of the thin steel shells, taking the original thickness of a steel lining, and simplifying the whole nuclear containment into a thin shell composed of a steel bar layer, the prestressed tendons and a steel lining layer; and gradually calculating the stress and the strain of the containment vessel until the containment vessel is damaged by taking the pressure difference between the inside and the outside of the containment vessel as a load condition and increasing the load from 0 to obtain the ultimate bearing capacity. According to the method, the simplified calculation of the nuclear containment is realized, and the method has the advantages of accuracy and universality.

Description

technical field [0001] The invention relates to the technical field of nuclear power, in particular to a calculation method for the pressure bearing performance of a nuclear containment vessel. Background technique [0002] The safe and efficient development of nuclear energy is one of the important measures to optimize the energy structure, promote industrial upgrading and integrated development, ensure national security and build an ecological civilization. As the third barrier of the nuclear power plant, the containment vessel is the last barrier of the defense-in-depth system, and its integrity and reliability are crucial to the safety of the nuclear power plant. [0003] The nuclear containment vessel is generally composed of reinforced concrete and steel lining. Under high pressure, the concrete is easy to crack, and the steel lining, steel bars in the concrete, and prestressed tendons jointly resist the internal pressure. During the operation of a nuclear power plant...

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Problems solved by technology

[0004] Patent CN111189594A discloses a method for rapid assessment of the leakage rate of multilayer pressure-bearing shells based on the principle of flow conservation. The circumferential strain distribution of each layer of shells is based on the estimation of the circumferential crack opening on the basis of exceeding the tensile limit strain of the material. This invention can estimate the cracking of multi-layer pressure-bearing shells under the internal pressure of severe accidents, and quickly evaluate the cracking degree The gas leakage rate of different multi-layer shell walls, however: a) This patent aims to evaluate the leakage rate of the containment vessel, and lacks consideration for the bearing capacity of the structure, while this application can calculate the ultimate load that the containment vessel can bear, making up for This shortcoming; b) The patent uses the assumption of an ideal

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