A method for analyzing the influence of main bolt fracture on the performance of pressure vessels
A pressure vessel and analysis method technology, applied in the direction of instrumentation, geometric CAD, design optimization/simulation, etc., can solve problems such as not retrieved, and achieve a wide range of effects
Active Publication Date: 2022-07-29
NUCLEAR POWER INSTITUTE OF CHINA
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Problems solved by technology
[0004] At present, there are literatures published on the techniques of reactor pressure vessel seal analysis, stress and fatigue analysis, and main bolt thread defect analysis, but the effects of bolt fracture and fracture in different combinations of multiple bolts on the stress, fatigue and sealing performance of pressure vessels have been published. Impact analysis method, no relevant technical literature has been retrieved
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[0029] Taking the reactor pressure vessel of a nuclear power project as an example, the method of calculating and using the present invention is as follows:
[0030] 1) Use the mechanical analysis software ANSYS to establish an analysis model of the reactor pressure vessel. The analysis includes the pressure vessel top cover, top cover flange, vessel flange, pressure vessel barrel, and main bolts. The analysis model must establish a sufficient number of main bolts, and must The other main bolts affected after the main bolt is broken are built in the model;
[0031] Specifically, as figure 1 As shown in the figure, the calculation model including the pressure vessel top cover, top cover flange, vessel flange, pressure vessel cylinder, and main bolts is established by combining shell elements, rod elements and solid elements. The analysis model contains 22 main bolt;
[0032] 2) Assume that the different main bolts in 6 have different fracture modes, such as figure 2 shown, ...
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The invention discloses a method for analyzing the influence of main bolt fracture on the performance of a pressure vessel. The method includes the following steps: establishing an analysis model of the pressure vessel, and the analysis model must establish a sufficient number of bolts; applying a load, calculating the main bolt fracture and multiple The sealing performance of the pressure vessel when the main bolts are broken in different combinations and the change of the force of other adjacent bolts affected by the broken bolts; establish a pressure vessel model containing half of the main bolts to carry out the sealing when the structure is intact, that is, the main bolts are not broken. Performance, stress and fatigue analysis; based on the above results, calculate the sealing performance of the pressure vessel under the fracture condition of multiple main bolts in different combinations and the stress and fatigue results of the pressure vessel flange and bolts; the present invention can realize the fracture of the main bolt and the multiple Analysis of the influence of different combinations of main bolts on the stress, fatigue and sealing performance of pressure vessels.
Description
technical field [0001] The invention relates to the field of reactor structure mechanics analysis, in particular to a method for analyzing the influence of main bolt fracture on the performance of a pressure vessel. Background technique [0002] With the gradual increase in the number of nuclear power projects put into operation and under construction in my country, the occurrence of defects in the processing and production of reactor pressure vessels and in the in-service stage is becoming more and more frequent. The typical and serious defects are main bolt defects, including thread Defects, reduced bolt pre-tightening force, bolt stress relaxation and bolt fracture, etc., the above conditions will reduce the sealing performance of the pressure vessel, and at the same time, the stress and fatigue results of the pressure vessel flange and bolts will increase, jeopardizing the normal and safe operation of the nuclear power plant. . [0003] In the case of serious thread defec...
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IPC IPC(8): G06F30/20G06F30/17G06F119/14
CPCG06F30/17G06F30/20G06F2119/06
Inventor 郑连纲吕勇波白晓明王新军卢喜丰艾红雷张锐何风袁艳丽袁锋杨凯杨杰
Owner NUCLEAR POWER INSTITUTE OF CHINA