Nuclear reactor monitoring method and system
A nuclear reactor and channel technology, applied in the field of nuclear reactors, can solve the problems of inaccurate nuclear reactor monitoring results, difficulty in obtaining mass flow, inlet pressure and outlet pressure, etc.
Pending Publication Date: 2021-12-14
NO 719 RES INST CHINA SHIPBUILDING IND
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[0004] The present invention provides a nuclear reactor monitoring method and system, which is used to solve the problem that it is difficult to obtain accurate mass flow rate, inlet pressure and Outlet pressure, leading to inaccurate monitoring results of nuclear reactor defects, to achieve accurate monitoring of nuclear reactors
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[0044] In order to make the purpose, technical solutions and advantages of the present invention clearer, the technical solutions in the present invention will be clearly and completely described below in conjunction with the accompanying drawings in the present invention. Obviously, the described embodiments are part of the embodiments of the present invention , but not all examples. Based on the embodiments of the present invention, all other embodiments obtained by persons of ordinary skill in the art without creative efforts fall within the protection scope of the present invention.
[0045] Combine below figure 2 The nuclear reactor monitoring method of the present invention is described, including: step 201, using a dynamic grid model to divide the fluid area of each channel in the nuclear reactor into a plurality of control bodies;
[0046] Among them, the dynamic mesh model can be used to simulate the problem that the shape of the flow field changes with time due t...
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The invention provides a nuclear reactor monitoring method and system. The method comprises the following steps: dividing a fluid area of each channel in a nuclear reactor into a plurality of control bodies by adopting a dynamic grid model; adding the liquid level heights of all the control bodies of all the channels at the current moment to obtain the liquid level heights of all the channels, and obtaining the outlet pressure of the ascending channel and the inlet pressure of the descending channel in any two communicated channels according to the liquid level heights of all the channels; according to the outlet pressure of the ascending channel and the inlet pressure of the descending channel in the two channels, calculating the mass flow of a through hole connecting any two communicated channels based on a first momentum conservation equation; and determining whether the nuclear reactor is normal or not according to the mass flow of each channel, the liquid level height, the inlet pressure, the outlet pressure and the mass flow of the through hole. According to the method, the liquid level height is combined with the momentum conservation equation established according to the thermal hydraulic parameter characteristics, so that more accurate thermal hydraulic parameters are obtained, and a more accurate monitoring result of the nuclear reactor is obtained.
Description
technical field [0001] The invention relates to the technical field of nuclear reactors, in particular to a nuclear reactor monitoring method and system. Background technique [0002] At present, in the modeling and calculation of thermal-hydraulic parameters of nuclear reactors, the thermal-hydraulic parameters of nuclear reactors are mainly calculated and obtained based on three-dimensional VOF (Volume Of Fluid, volume of fluid function) method modeling. This method is more effective for detecting local thermal-hydraulic characteristics. However, the calculation of this three-dimensional VOF method is complex and requires many parameters. It is embedded in the nuclear reactor safety system program, which seriously affects the calculation efficiency of the nuclear reactor safety system program. Therefore, in the safety design of the reactor, the system program calculation based on the one-dimensional method has more practical significance. [0003] However, in the calcula...
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Login to View More IPC IPC(8): G06F30/23G06F30/28G21C17/032G06F113/08G06F119/14
CPCG06F30/23G06F30/28G21C17/032G06F2119/14G06F2113/08Y02E30/30
Inventor 宋苹冯唐涛陈冲陈列戴春辉劳星胜李少丹代路赵振兴李勇林原胜柯志武
Owner NO 719 RES INST CHINA SHIPBUILDING IND