Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software

A technology of stress analysis and static analysis, which is applied in the direction of instruments, special data processing applications, electrical digital data processing, etc., can solve the problems of cumbersome analysis, time-consuming and labor-intensive, high cost, etc., to improve calculation accuracy, improve analysis efficiency, Effect of reducing design cost

Active Publication Date: 2011-09-14
大连船舶重工集团装备制造有限公司
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Problems solved by technology

Analytical analysis methods need to find a compromise between the structure and the accuracy of the results. The actual structure is generally more complex, and it is very cumbersome to analyze and analyze it.
The experimental method has incomparable advantages in its accuracy, but its disadvantages are also very prominent, such as high cost, complicated operation, time-consuming and labor-intensive. Generally, this method is used for final strength verification before the design is finalized and put into use, which is not suitable for the design process. used in

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  • Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software
  • Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software
  • Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software

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Embodiment Construction

[0045] The ANSYS stress analysis method of the first-class nuclear vessel uses ANSYS software to write a parametric design program. Bearing 5 etc. carry out detailed stress analysis and calculation under design conditions, operating conditions and test conditions, conduct seismic response spectrum analysis on the overall equipment, conduct contact analysis on flange bolts, and perform different types of stress in accordance with ASME code requirements Carry out classification and intensity assessment.

[0046] The ANSYS stress analysis method of the nuclear first-class container, firstly, after the conventional design is carried out according to the design specifications, the design drawing is given, the geometric model and the finite element model are established by simulating the equipment in ANSYS, and all nuclear-level components are analyzed and calculated, and the stress analysis results are extracted , in accordance with ASME volume III, NB, NF sub-volume requirements f...

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Abstract

The invention discloses a method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software, belonging to the technical field of analysis and design methods for first-class nuclear reactors. The method comprises the following steps: firstly, after carrying out routine design according to a design specification, thus obtaining a design drawing; establishing a geometric model and a finite element model by using a simulation device in an ANSYS; carrying out analysis and calculation on all nuclear parts; extracting a stress analysis result; and carrying out strength assessment according to the specifications stipulated in subsections NB and NF of section III of ASME (American society of mechanical engineers), then obtaining a detailed design report. Compared with the prior art, the method disclosed by the invention summarizes and improves a method for carrying out analysis and design on first-class nuclear reactors through using ANSYS software; compared with an analytical method and a test method, by using the method disclosed by the invention, the design time is greatly shortened, the design expense is reduced, the analysis efficiency is greatly improved, and the analysis cost is reduced; and in the process of analysis, an entity is adopted for modeling a hexahedron unit, thereby improving the calculation accuracy.

Description

technical field [0001] The invention relates to an ANSYS stress analysis method for a nuclear primary container, and belongs to the technical field of analysis and design methods for a nuclear primary container. Background technique [0002] According to ASME volume III, NB sub-volume requirements, nuclear primary equipment is different from the rule-based design of general pressure vessels, and must be analyzed and designed. The failure criterion based on the rule-based design is the elastic failure criterion, and the analysis design considers the plastic failure criterion and elastic-plastic failure criterion, and introduces the concept of safe life, and performs fatigue analysis on components with cyclic loading characteristics. The quantitative analysis results make the structure more reasonable. The core of the analysis and design process is to do the necessary stress analysis on the components, and then carry out the stress classification check according to the stress...

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/50
Inventor 吕岩潘清泉秦大秋
Owner 大连船舶重工集团装备制造有限公司
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