Method for analyzing influence of main bolt breakage on performance of a pressure container
A pressure vessel and analysis method technology, applied in the direction of instrumentation, geometric CAD, calculation, etc., can solve problems such as not retrieved, and achieve a wide range of effects
Active Publication Date: 2019-03-19
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 a certain nuclear power project reactor pressure vessel as an example, calculating and using the method of the present invention are as follows:
[0030] 1) Use the mechanical analysis software ANSYS to establish the analysis model of the reactor pressure vessel. The analysis includes the pressure vessel top cover, top cover flange, vessel flange, pressure vessel cylinder, and main bolts. The analysis model must establish a sufficient number of main bolts. The other main bolts that are affected after the main bolt is broken are established in the model;
[0031] Specifically, such as figure 1 As shown, the calculation model including the roof of the pressure vessel, the flange of the roof, the flange of the pressure vessel, the cylinder of the pressure vessel and the main bolt is established by combining the shell element, the rod element and the solid element. The analysis model includes 22 main bolt;
[0032] 2) Assumption 6 in the fracture modes of different...
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The invention discloses a method for analyzing the influence of main bolt breakage on the performance of a pressure container, which comprises the following steps of: establishing a pressure containeranalysis model, and establishing enough bolt quantity for the analysis model; applying a load, and calculating the sealing performance of the pressure vessel under the conditions of breakage of the main bolts and breakage of a plurality of main bolts in different combination modes, and the change condition of the stress of other adjacent bolts influenced by the breakage of the bolts; establishinga pressure vessel model containing half main bolts to carry out structural integrity, i.e., sealing performance, stress and fatigue analysis when the main bolts are not fractured; calculating the sealing performance of the pressure vessel and the stress and fatigue results of the pressure vessel flange and the bolts under the condition that the plurality of main bolts are fractured in different combination modes based on the result; according to the invention, influence analysis on stress, fatigue and sealing performance of the pressure vessel under the conditions of breakage of the main bolts and breakage of multiple main bolts in different combination modes can be realized.
Description
technical field [0001] The invention relates to the field of reactor structural mechanics analysis, in particular to an analysis method for 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, defects occur more and more frequently in the processing and production process of reactor pressure vessels and in the service stage. Among them, the more typical and serious defects are main bolt defects, including thread Defects, reduction of bolt pre-tightening force, bolt stress relaxation, and bolt breakage, etc., will reduce the sealing performance of the pressure vessel, and at the same time, the stress and fatigue of the pressure vessel flange and bolts will increase, endangering the normal and safe operation of the nuclear power plant. . [0003] In the case of serious thread defects, if there is no repl...
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IPC IPC(8): G06F17/50
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