A method of assessing safe operation of a reactor
A technology for safe operation and reactors, applied in special data processing applications, instruments, electrical digital data processing, etc., can solve problems that affect the safety and reliability of RPV, the economic benefits of nuclear power plants, and unsatisfactory technical solutions.
Active Publication Date: 2019-05-24
CHINA INSTITUTE OF ATOMIC ENERGY
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Problems solved by technology
Once the serious embrittlement of RPV occurs during service, it will directly threaten the operation safety of the reactor, and the nuclear power plant must be shut down in advance, which will undoubtedly have a serious impact on the economic benefits of the nuclear power plant, and welds are the weak link of RPV. It directly affects the safety and reliability of the entire RPV
[0003] None of the current technical solutions for assessing the safe operation of reactors are satisfactory
Method used
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Embodiment
[0082] Ni-Cr-Mo-V steel weld material T for a certain VVER-1000 type RPV as an embodiment K The relationship between the experimental value and the P concentration at the grain boundary is as figure 2 shown. A linear fit is performed on the data in the figure to obtain:
[0083] T K (t)=-74.13℃+521.74℃ / at.%C b (t)
[0084] Then the grain boundary P concentration prediction model, where α n for the equation The nth solution of :
[0085]
[0086] brought into T K T K Prediction model:
[0087]
[0088] Compare the obtained prediction model results with the results obtained from the experimental data, and the comparison results are as follows: figure 2 shown, from figure 2 It can be seen that the prediction model is in good agreement with the experimental point 2, which verifies the reliability of the parameter calculation method and the model itself. It should be noted that the experimental point 1 participates in the model calculation and does not make com...
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The invention relates to a method for assessing safe operation of a reactor, comprising the following steps: substituting a time parameter t into a reactor pressure vessel weld joint thermal aging ductile-brittle transition temperature value TK change prediction model, and determining whether the reactor pressure vessel operates safely or not according to comparison of a result and an operation temperature; acquiring the TK change prediction model for the thermal aging ductile-brittle transition temperature value of the reactor pressure vessel welding seam through the following steps that (1)conducting linear fitting on experimental data, and a linear relation between TK and the grain boundary P concentration is obtained; and (2) substituting the grain boundary P concentration predictionmodel into a linear relation between the TK and the grain boundary P concentration to obtain a TK prediction model. The method has the beneficial effects that the TK prediction model is established topredict the TK of the RPV welding line material, and the safety and reliability of reactor operation are evaluated. the prediction model only contains one variable of time t, so that great convenience is brought to the realization of TK prediction.
Description
technical field [0001] The invention relates to the technical field of reactor pressure vessel safety assessment, in particular to a method for evaluating the safe operation of a reactor. Background technique [0002] The reactor pressure vessel (RPV) is the most important key equipment of the pressurized water reactor nuclear power plant. It wraps the reactor active area and other necessary equipment and cannot be replaced during the lifetime of the reactor. The reliability of its performance directly determines the service life of the nuclear power plant. It is related to the economy and safety of nuclear power plant operation. Since RPV has been operating under the conditions of high temperature, high pressure and strong radiation field for a long time, its aging embrittlement behavior is very complex, mainly including thermal aging embrittlement and radiation embrittlement. Once the serious embrittlement of RPV occurs during service, it will directly threaten the operat...
Claims
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IPC IPC(8): G06F17/50
Inventor 王成龙佟振峰林虎宁广胜张长义杨文
Owner CHINA INSTITUTE OF ATOMIC ENERGY