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Stress Evaluation Of Vessel Velocity And Lower Tables For Large - Scale Pre - Pressure Pressure Oil Tower

Posted on:2016-08-20Degree:MasterType:Thesis
Country:ChinaCandidate:Y H HuoFull Text:PDF
GTID:2132330461999914Subject:Safety Technology and Engineering
Abstract/Summary:PDF Full Text Request
As a safe, economic, clean and sustainable development way of generating electricity, nuclear energy has been accepted by the society, nuclear power is also a part of China’s energy strategy, its proportion in total energy supply will increase gradually. Promoting nuclear power construction actively is an important national energy strategy, which has the important significance for meeting the growing energy demand of the economic and social development, realizing the coordinated development of energy, economy and ecological environment, and enhancing the comprehensive economic strength and the level of industrial technology of China.The reactor pressure vessel is an important equipment of the reactor coolant pressure boundary barrier in a nuclear power plant. It is mainly used for loading the reactor core, sealing the high temperature, high pressure coolant, guiding and positioning the necessary core control and reactor measurement for the reactor safety operation. The reactor pressure vessel is a kind of level I safety equipments, therefore, it must maintain the reliable structural integrity in various working conditions, which can ensure that container damage and radioactive leak will not occur. The shell is the main component of pressure vessel, it is together with the head or tube plate to form the bearing shell, which provides the necessary bearing space for materials storage, physical and chemical reactions, and some other technology use. The lower closure head is an important component for ensuring sealed pressure vessel. Therefore, the safety of the lower shell and the lower closure head is crucial for their design and use, the implementation of their stress assessment is very necessary.This paper takes the large-scale advanced pressurized water reactor nuclear power plant pressure vessel cylinder shell and the lower closure head as the research object, according to the relevant requirements of the ASME “boiler and pressure vessel standard’’, based on the finite element method, this paper has completed primary stress strength calculation, analysis and evaluation of the reactor pressure vessel lower shell and lower closure head under various loads of various working conditions, and analysis of the influence of various load on stress distribution. Finally this paper obtains the conclusion that the structure strength meets specification requirements. On this basis, through simplifying the whole model, this paper establishes the local model, carries out further stress evaluation of the lower shell and lower closure head, the calculated results are compared with the results of the whole model. The research results of this paper can provide technical support for the design of pressure vessels.
Keywords/Search Tags:large-scale advanced PWR, pressure vessels, lower shell and lower closure head, stress evaluation, local mode
PDF Full Text Request
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