A Method for Evaluating the Safe Operation of Reactors
A technology for safe operation and reactor, applied in the direction of design optimization/simulation, etc., can solve the problems of unsatisfactory technical solution effect, impact on economic benefits of nuclear power plants, impact on safety and reliability of RPV, etc.
Active Publication Date: 2020-10-09
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] As an example, a certain VVER-1000 type RPV used Ni-Cr-Mo-V steel weld material T K The relationship between the experimental value and the P concentration at the grain boundary is as follows figure 2 Shown. Perform linear fitting on the data in the figure to get:
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[0084]
[0085] Bring in to T K The linear relationship with the concentration of P at the grain boundary can get T K Forecast model:
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[0087] Compare the results of the prediction model 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 is not compared.
[0088] among them, Figure 5 Shown is the accumulation composition curve of P element at the grain ...
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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 technical field of reactor pressure vessel safety assessment of the present invention specifically relates to a method for assessing the safe operation of a reactor. Background technique [0002] Reactor pressure vessel (RPV), as the most important key equipment of a pressurized water reactor nuclear power plant, wraps the reactor active area and other necessary equipment and cannot be replaced during the entire life 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. Because RPV has been operating under high temperature, high pressure and strong radiation field conditions for a long time, its aging embrittlement behavior is very complicated, mainly including thermal aging embrittlement and irradiation embrittlement. Once severe embrittlement of RPV occurs during service, which will directly threaten the safety of re...
Claims
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IPC IPC(8): G06F30/20
Inventor 王成龙佟振峰林虎宁广胜张长义杨文
Owner CHINA INSTITUTE OF ATOMIC ENERGY