CN115493665A - A method, device, and storage medium for monitoring helium-water flow in a high-temperature gas-cooled reactor - Google Patents
A method, device, and storage medium for monitoring helium-water flow in a high-temperature gas-cooled reactor Download PDFInfo
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Abstract
Description
技术领域technical field
本申请涉及核反应堆工程技术领域,尤其涉及一种高温气冷堆氦水流量的监测方法、装置及存储介质。The present application relates to the technical field of nuclear reactor engineering, in particular to a method, device and storage medium for monitoring the helium-water flow rate of a high-temperature gas-cooled reactor.
背景技术Background technique
高温气冷堆的主冷却剂为氦气,并通过氦气流动将反应堆堆芯核燃料产生的热量带出送至蒸汽发生器一次侧,然后热量在蒸汽发生器中传递,由蒸汽发生器二次侧中流动的水带走,流动的水在蒸汽发生器中转化为蒸汽,送至汽轮发做功,汽轮机带动发电机转动,从而产生电能。The main coolant of the high temperature gas-cooled reactor is helium, and through the flow of helium, the heat generated by the nuclear fuel of the reactor core is taken out and sent to the primary side of the steam generator, and then the heat is transferred in the steam generator, and is sent to the secondary side of the steam generator. The water flowing in the side is taken away, and the flowing water is converted into steam in the steam generator, and sent to the steam turbine to do work, and the steam turbine drives the generator to rotate, thereby generating electric energy.
其中,上述高温气冷堆能量的转移过程依赖于氦气的流动和水的流动,基于此需要实时监测氦气流量和水的流量是否匹配,若氦气流量和水的流量不匹配,则会对能量的转移产生影响,从而导致气冷堆自动停堆,进而对气冷堆进行破坏。Among them, the above-mentioned high-temperature gas-cooled reactor energy transfer process depends on the flow of helium and water. Based on this, it is necessary to monitor whether the flow of helium and the flow of water match in real time. If the flow of helium does not match the flow of water, it will It affects the transfer of energy, which leads to the automatic shutdown of the gas-cooled reactor, and then destroys the gas-cooled reactor.
相关技术中,通过运维人员定期观测反应堆内氦气流量和蒸汽发生器内给水流量,并通过计算得出氦气流量和给水流量是否匹配。但是,相关技术中的运维人员定期观测并不能达到实时判断的效果,并且人工计算可能会产生失误,使得计算结果不准确,从而导致高温气冷堆的停堆停机产生不必要的损失。In related technologies, operation and maintenance personnel regularly observe the helium flow in the reactor and the feedwater flow in the steam generator, and calculate whether the helium flow and the feedwater flow match. However, regular observation by operation and maintenance personnel in related technologies cannot achieve real-time judgment results, and manual calculations may cause errors, making the calculation results inaccurate, resulting in unnecessary losses caused by the shutdown of the high-temperature gas-cooled reactor.
发明内容Contents of the invention
本申请提供一种高温气冷堆氦水流量的监测方法、装置及存储介质,以解决上述相关技术中出现的技术问题。The present application provides a method, device and storage medium for monitoring the flow of helium water in a high-temperature gas-cooled reactor, so as to solve the technical problems in the above-mentioned related technologies.
本申请第一方面实施例提出一种高温气冷堆氦水流量的监测方法,所述氦水流量包括氦气流量和给水流量,所述方法包括:The embodiment of the first aspect of the present application proposes a method for monitoring the helium water flow rate of a high temperature gas-cooled reactor, the helium water flow rate includes the helium gas flow rate and the feed water flow rate, and the method includes:
获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率;Obtain the current helium flow, feed water flow and nuclear power of each monitoring channel in multiple different monitoring channels;
根据所述各个监测通道的氦气流量和给水流量,计算所述各个监测通道当前的氦水流量比;Calculate the current helium-water flow ratio of each monitoring channel according to the helium flow and the feed water flow of each monitoring channel;
根据所述各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值;Calculate the nuclear power ratio corresponding to the current high temperature gas-cooled reactor according to the nuclear power of each monitoring channel;
获取高温气冷堆对应的氦水流量比限值曲线;Obtain the helium-water flow ratio limit curve corresponding to the high-temperature gas-cooled reactor;
根据所述氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于所述氦水流量比的限值对所述各个监测通道的氦水流量比进行监测。The limit value of the helium-water flow ratio corresponding to the current nuclear power ratio is obtained according to the limit value curve of the helium-water flow ratio, and the helium-water flow ratio of each monitoring channel is monitored based on the limit value of the helium-water flow ratio.
本申请第二方面实施例提出一种高温气冷堆氦水流量的监测装置,所述氦水流量包括氦气流量和给水流量,所述装置包括:The embodiment of the second aspect of the present application proposes a monitoring device for the flow of helium water in a high temperature gas-cooled reactor, the flow of helium water includes the flow of helium gas and the flow of feed water, and the device includes:
第一获取模块,用于获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率;The first acquisition module is used to acquire the current helium flow rate, feed water flow rate and nuclear power of each monitoring channel in a plurality of different monitoring channels;
第一计算模块,用于根据所述各个监测通道的氦气流量和给水流量,计算所述各个监测通道当前的氦水流量比;The first calculation module is used to calculate the current helium-water flow ratio of each monitoring channel according to the helium flow rate and the feed water flow rate of each monitoring channel;
第二计算模块,用于根据所述各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值;The second calculation module is used to calculate the nuclear power ratio corresponding to the current high temperature gas-cooled reactor according to the nuclear power of each monitoring channel;
第二获取模块,用于获取高温气冷堆对应的氦水流量比限值曲线;The second acquisition module is used to acquire the helium-water flow ratio limit curve corresponding to the high-temperature gas-cooled reactor;
监测模块,用于根据所述氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于所述氦水流量比的限值对所述各个监测通道的氦水流量比进行监测。本申请第三方面实施例提出的计算机存储介质,其中,所述计算机存储介质存储有计算机可执行指令;所述计算机可执行指令被处理器执行后,能够实现如上第一方面所述的方法。A monitoring module, configured to obtain the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the limit value curve of the helium-water flow ratio, and adjust the helium-water flow rate of each monitoring channel based on the limit value of the helium-water flow ratio than monitor. The computer storage medium provided by the embodiment of the third aspect of the present application, wherein the computer storage medium stores computer-executable instructions; after the computer-executable instructions are executed by a processor, the method described in the first aspect above can be implemented.
本申请第四方面实施例提出的计算机设备,其中,包括存储器、处理器及存储在存储器上并可在处理器上运行的计算机程序,处理器执行所述程序时,能够实现如上第一方面所述的方法。The computer equipment proposed in the embodiment of the fourth aspect of the present application includes a memory, a processor, and a computer program stored in the memory and operable on the processor. When the processor executes the program, it can realize the above-mentioned first aspect. described method.
本申请的实施例提供的技术方案至少带来以下有益效果:The technical solutions provided by the embodiments of the present application bring at least the following beneficial effects:
本申请提出的高温气冷堆氦水流量的监测方法、装置及存储介质中,获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率,根据各个监测通道的氦气流量和给水流量,计算各个监测通道当前的氦水流量比,根据各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值,获取高温气冷堆对应的氦水流量比限值曲线,根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对各个监测通道进行监测。由此,本申请可以计算各个监测通道的氦水流量比,不需要依赖人工计算,以使得计算结果更加准确、直观。同时,通过氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,并基于氦水流量比的限值对各个监测通道的氦水流量比进行监测,实现了对气冷堆实时观测,从而避免高温气冷堆产生不必要停堆停机损失。In the monitoring method, device and storage medium of the high temperature gas-cooled reactor helium water flow rate proposed by the application, the current helium flow rate, feed water flow rate and nuclear power of each monitoring channel in a plurality of different monitoring channels are obtained, and according to the helium flow rate of each monitoring channel Flow and feed water flow, calculate the current helium-water flow ratio of each monitoring channel, calculate the current nuclear power ratio corresponding to the high-temperature gas-cooled reactor according to the nuclear power of each monitoring channel, and obtain the helium-water flow ratio limit curve corresponding to the high-temperature gas-cooled reactor , obtain the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the limit value curve of the helium-water flow ratio, and monitor each monitoring channel based on the limit value of the helium-water flow ratio. Therefore, the present application can calculate the helium-water flow ratio of each monitoring channel without relying on manual calculation, so that the calculation result is more accurate and intuitive. At the same time, the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio is obtained through the limit value curve of the helium-water flow ratio, and the helium-water flow ratio of each monitoring channel is monitored based on the limit value of the helium-water flow ratio. Real-time observation of the cold reactor, so as to avoid unnecessary shutdown losses of the high-temperature gas-cooled reactor.
本申请附加的方面和优点将在下面的描述中部分给出,部分将从下面的描述中变得明显,或通过本申请的实践了解到。Additional aspects and advantages of the application will be set forth in part in the description which follows, and in part will be obvious from the description, or may be learned by practice of the application.
附图说明Description of drawings
本申请上述的和/或附加的方面和优点从下面结合附图对实施例的描述中将变得明显和容易理解,其中:The above and/or additional aspects and advantages of the present application will become apparent and easy to understand from the following description of the embodiments in conjunction with the accompanying drawings, wherein:
图1为根据本申请一个实施例提供的高温气冷堆氦水流量的监测方法的流程示意图;Fig. 1 is a schematic flow chart of a method for monitoring the flow of helium water in a high temperature gas-cooled reactor according to an embodiment of the present application;
图2为根据本申请一个实施例提供的高温气冷堆氦水流量的监测方法输出的示意图;Fig. 2 is the schematic diagram that the monitoring method output of the high temperature gas-cooled reactor helium water flow rate provided according to one embodiment of the present application;
图3为根据本申请一个实施例提供的高温气冷堆氦水流量的监测装置的结构示意图。Fig. 3 is a schematic structural diagram of a monitoring device for helium-water flow in a high-temperature gas-cooled reactor according to an embodiment of the present application.
具体实施方式detailed description
下面详细描述本申请的实施例,所述实施例的示例在附图中示出,其中自始至终相同或类似的标号表示相同或类似的元件或具有相同或类似功能的元件。下面通过参考附图描述的实施例是示例性的,旨在用于解释本申请,而不能理解为对本申请的限制。Embodiments of the present application are described in detail below, examples of which are shown in the drawings, wherein the same or similar reference numerals denote the same or similar elements or elements having the same or similar functions throughout. The embodiments described below by referring to the figures are exemplary, and are intended to explain the present application, and should not be construed as limiting the present application.
下面参考附图描述本申请实施例的高温气冷堆氦水流量的监测方法及装置。The method and device for monitoring the flow of helium water in a high temperature gas-cooled reactor according to the embodiments of the present application will be described below with reference to the accompanying drawings.
实施例一Embodiment one
图1为根据本申请一个实施例提供的一种高温气冷堆氦水流量的监测方法的流程示意图,如图1所示,可以包括:Fig. 1 is a schematic flow chart of a method for monitoring the flow of helium water in a high temperature gas-cooled reactor according to an embodiment of the present application. As shown in Fig. 1 , it may include:
步骤101、获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率。
其中,在本公开实施例中,氦水流量包括氦气流量和给水流量。Wherein, in the embodiment of the present disclosure, the flow rate of helium water includes the flow rate of helium gas and the flow rate of feed water.
以及,在本公开实施例中,上述多个不同监测通道可以为4个不同的监测通道,其中每个监测通道均可监测当前的氦气流量、给水流量和对应的和核功率。And, in the embodiment of the present disclosure, the above-mentioned multiple different monitoring channels may be 4 different monitoring channels, wherein each monitoring channel can monitor the current helium gas flow, feed water flow and corresponding nuclear power.
步骤102、根据各个监测通道的氦气流量和给水流量,计算各个监测通道当前的氦水流量比。Step 102: Calculate the current helium-water flow ratio of each monitoring channel according to the helium flow rate and the feed water flow rate of each monitoring channel.
其中,在本公开实施例中,上述每个监测通道当前的氦水流量比=氦气流量/给水流量。Wherein, in the embodiment of the present disclosure, the current helium-to-water flow ratio of each monitoring channel=helium flow/feedwater flow.
以及,在本公开实施例中,通过氦水流量比判断当前的氦气流量和给水流量是否匹配。And, in the embodiment of the present disclosure, it is judged whether the current helium gas flow and the feed water flow match according to the helium-water flow ratio.
步骤103、根据各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值。Step 103: Calculate the nuclear power ratio corresponding to the current high temperature gas-cooled reactor according to the nuclear power of each monitoring channel.
其中,在本公开实施例中,计算当前高温气冷堆对应的核功率比值的方法可以包括:根据各个监测通道的核功率,计算平均核功率,并根据平均核功率和高温气冷堆的额定功率,计算当前高温气冷堆对应的核功率比值。Among them, in the embodiment of the present disclosure, the method for calculating the nuclear power ratio corresponding to the current high-temperature gas-cooled reactor may include: calculating the average nuclear power according to the nuclear power of each monitoring channel, and calculating the average nuclear power according to the average nuclear power and the rated value of the high-temperature gas-cooled reactor Power, calculate the nuclear power ratio corresponding to the current high temperature gas-cooled reactor.
具体的,在本公开实施例中,上述计算平均核功率时,可以将多个监测通道的核功率进行求和得到总核功率,然后将总核功率除以监测通道的个数得到平均核功率。示例的,假设高温气冷堆有4个监测通道,且4个监测通道对应的核功率分别为PA,PB,PC,PD,则平均核功率=(PA+PB+PC+PD)/4。Specifically, in the embodiment of the present disclosure, when calculating the average nuclear power above, the nuclear power of multiple monitoring channels can be summed to obtain the total nuclear power, and then the total nuclear power can be divided by the number of monitoring channels to obtain the average nuclear power . For example, assuming that the high-temperature gas-cooled reactor has 4 monitoring channels, and the nuclear powers corresponding to the 4 monitoring channels are PA, P B , PC, and PD respectively, then the average nuclear power = (PA + P B + P C +P D )/4.
以及,在本公开实施例中,上述核功率比值为平均核功率与高温气冷堆的额定功率的比值,并用百分比的形式进行表示,例如,核功率比值为50%。And, in the embodiment of the present disclosure, the above-mentioned nuclear power ratio is the ratio of the average nuclear power to the rated power of the high temperature gas-cooled reactor, and is expressed in the form of a percentage, for example, the nuclear power ratio is 50%.
步骤104、获取高温气冷堆对应的氦水流量比限值曲线。
其中,在本公开实施例中,上述氦水流量比限值曲线包括氦水流量比上限值曲线和氦水流量比下限值曲线。Wherein, in the embodiment of the present disclosure, the helium-water flow ratio limit curve includes a helium-water flow ratio upper limit curve and a helium-water flow ratio lower limit curve.
以及,在本公开实施例中,氦水流量比上限值曲线是根据第一公式得到的,其中,第一公式为:y1=k1ⅹP+a,k1为反应堆安全分析的斜率关系,a为反应堆安全分析得到的理论偏差,P为核功率比值。其中,通过第一公式可以得出,氦水流量比上限值曲线的横坐标为核功率比值,纵坐标为核功率比值对应的氦水流量比的上限值。And, in the embodiment of the present disclosure, the helium-water flow ratio upper limit curve is obtained according to the first formula, wherein the first formula is: y 1 =k 1 ⅹP+a, and k 1 is the slope relationship of the reactor safety analysis , a is the theoretical deviation obtained from the reactor safety analysis, and P is the nuclear power ratio. Wherein, it can be obtained from the first formula that the abscissa of the helium-to-water flow ratio upper limit curve is the nuclear power ratio, and the ordinate is the upper limit of the helium-to-water flow ratio corresponding to the nuclear power ratio.
在本公开实施例中,氦水流量比下限值曲线是根据第二公式得到的,其中第二公式为:y2=k2ⅹP+b,k1为反应堆安全分析的斜率关系,a为反应堆安全分析得到的理论偏差,P为核功率比值。其中,通过第二公式可以得出,氦水流量比上限值曲线的横坐标为核功率比值,纵坐标为核功率比值对应的氦水流量比的下限值。In the embodiment of the present disclosure, the lower limit curve of the helium-water flow ratio is obtained according to the second formula, wherein the second formula is: y 2 =k 2 ⅹP+b, k1 is the slope relationship of the reactor safety analysis, and a is the reactor Theoretical deviation obtained from safety analysis, P is the ratio of nuclear power. Wherein, it can be obtained from the second formula that the abscissa of the helium-to-water flow ratio upper limit curve is the nuclear power ratio, and the ordinate is the lower limit of the helium-to-water flow ratio corresponding to the nuclear power ratio.
进一步地,在本公开实施例中,将当前核功率比值代入上述氦水流量比上限值曲线和氦水流量比下限值曲线中,可以得出当前核功率比值对应的氦水流量比的上限值和下限值,从而后续可以利用上限值和下限值判断当前氦水流量比是否匹配。Further, in the embodiment of the present disclosure, by substituting the current nuclear power ratio into the above-mentioned helium-water flow ratio upper limit curve and helium-water flow ratio lower limit curve, the helium-water flow ratio corresponding to the current nuclear power ratio can be obtained Upper limit value and lower limit value, so that the upper limit value and lower limit value can be used to judge whether the current helium-water flow ratio matches.
步骤105、根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对各个监测通道进行监测。Step 105: Obtain the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the limit value curve of the helium-water flow ratio, and monitor each monitoring channel based on the limit value of the helium-water flow ratio.
其中,在本公开实施例中,上述根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对所述各个监测通道的氦水流量比进行监测的方法可以包括以下步骤:Among them, in the embodiment of the present disclosure, the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio is obtained according to the limit value curve of the helium-water flow ratio, and the helium-water flow ratio of each monitoring channel is adjusted based on the limit value of the helium-water flow ratio. The method for monitoring flow ratio may include the following steps:
步骤a、根据氦水流量比上限值曲线获取当前核功率比值对应的氦水流量比的上限值。Step a: Obtain the upper limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the upper limit value curve of the helium-water flow ratio.
步骤b、根据氦水流量比下限值曲线获取当前核功率比值对应的氦水流量比的下限值。Step b. Obtain the lower limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the lower limit value curve of the helium-water flow ratio.
步骤c、基于氦水流量比的上限值和氦水流量比的下限值对当前各个监测通道的氦水流量比进行监测,若多个监测通道中存在监测通道的氦水流量比与上限值/下限值的差值超过预设偏差值,则进行报警。Step c, based on the upper limit value of the helium-water flow ratio and the lower limit value of the helium-water flow ratio, monitor the helium-water flow ratio of each monitoring channel at present. If the difference between the limit value/lower limit value exceeds the preset deviation value, an alarm will be issued.
其中,在本公开实施例中,若多个监测通道中各个监测通道的氦水流量比与上限值/下限值的差值均未超过预设偏差值,说明各个监测通道的氦水流量比正常,即各个监测通道的氦水流量和给水流量匹配,则不需要进行报警。Among them, in the embodiment of the present disclosure, if the difference between the helium-water flow ratio and the upper limit value/lower limit value of each monitoring channel among the multiple monitoring channels does not exceed the preset deviation value, it means that the helium-water flow rate of each monitoring channel If the ratio is normal, that is, the flow rate of helium water in each monitoring channel matches the flow rate of feed water, then no alarm is required.
以及,在本公开实施例中,若多个监测通道中存在监测通道的氦水流量比与上限值/下限值的差值超过预设偏差值,说明存在监测通道的氦水流量比已经非常靠近上限值/下限值,即该监测通道的氦水流量和给水流量不匹配,则需要进行报警,引起运维人员的注意,从而及时做出调整,避免高温气冷堆自动停堆。And, in the embodiment of the present disclosure, if the difference between the helium-water flow ratio of the monitoring channel and the upper limit value/lower limit value exceeds the preset deviation value among the multiple monitoring channels, it means that the helium-water flow ratio of the monitoring channel has been exceeded. Very close to the upper limit/lower limit, that is, the helium water flow of the monitoring channel does not match the feed water flow, an alarm needs to be issued to attract the attention of the operation and maintenance personnel, so as to make timely adjustments to avoid automatic shutdown of the high temperature gas-cooled reactor .
进一步地,在本公开实施例中,在多个监测通道中,氦水流量比与上限值/下限值的差值超过预设偏差值的监测通道的个数不一样时,对应的报警方式也不一样。Further, in the embodiment of the present disclosure, among multiple monitoring channels, when the number of monitoring channels whose difference between the helium-water flow ratio and the upper limit value/lower limit value exceeds the preset deviation value is different, the corresponding alarm The way is also different.
具体的,在本公开实施例中,假设高温气冷堆有4个监测通道,且仅有1个监测通道对应的氦水流量比与上限值/下限值的差值超过预设偏差值,此时可能单个监测通道的测量存在误差,可以进行排查,则对应的报警方式为输出报警,或者邮件提醒;有2个或2个以上监测通道对应的氦水流量比与上限值/下限值的差值超过预设偏差值,此时说明气冷堆处于危险的状态,有自动停堆的可能,则对应的报警方式为鸣笛,引起运维人员的注意,以便及时进行流量的调整。Specifically, in the embodiment of the present disclosure, it is assumed that the high-temperature gas-cooled reactor has 4 monitoring channels, and the difference between the helium-water flow ratio corresponding to only 1 monitoring channel and the upper limit value/lower limit value exceeds the preset deviation value , at this time, there may be an error in the measurement of a single monitoring channel, which can be checked, and the corresponding alarm method is an output alarm, or an email reminder; there are 2 or more monitoring channels corresponding to the helium-water flow ratio and the upper limit/down If the difference between the limit values exceeds the preset deviation value, it means that the gas-cooled reactor is in a dangerous state and there is a possibility of automatic shutdown, and the corresponding alarm method is to sound the whistle to attract the attention of the operation and maintenance personnel so that the flow rate can be monitored in time. Adjustment.
基于上述高温气冷堆氦水流量的监测方法的描述,上述监测方法还可以将各个监测通道的氦水流量比与氦水流量比上限值曲线和氦水流量比下限值曲线进行实时显示,以便运维人员可以实时监测。Based on the description of the monitoring method for the helium-water flow rate of the high-temperature gas-cooled reactor, the above-mentioned monitoring method can also display the helium-water flow ratio, the helium-water flow ratio upper limit curve and the helium-water flow ratio lower limit curve of each monitoring channel in real time , so that operation and maintenance personnel can monitor in real time.
具体的,在本公开实施例中,图2为本公开实施例提供的高温气冷堆氦水流量的监测方法输出的示意图。如图2所示,输出的页面会显示标题,标题为对应的核反应堆的标号,若标题显示为1#NSSS,即页面显示的数据与1#核反应堆对应;若标题显示2#NSSS,则页面显示的数据与2#核反应堆对应。Specifically, in the embodiment of the present disclosure, FIG. 2 is a schematic diagram of the output of the method for monitoring the flow of helium water in a high temperature gas-cooled reactor provided by the embodiment of the present disclosure. As shown in Figure 2, the output page will display the title, which is the label of the corresponding nuclear reactor. If the title is displayed as 1#NSSS, the data displayed on the page corresponds to the 1# nuclear reactor; if the title displays 2#NSSS, the page will display The data corresponds to the 2# nuclear reactor.
以及,如图2所示,页面左上角显示的实时参数为氦气流量、给水流量、氦水流量比、核功率。其中,显示的氦气流量、给水流量、氦水流量比、核功率均为气冷堆所有监测通道对应的平均值。以及,页面上还会显示每个监测通道对应的颜色圆点,如图2所示,在页面上用红、橙、黄、绿四个圆点分别标记A、B、C、D四个监测通道,每个圆点对应一个监测通道。And, as shown in Figure 2, the real-time parameters displayed in the upper left corner of the page are helium gas flow, feed water flow, helium-water flow ratio, and nuclear power. Among them, the displayed helium flow, feed water flow, helium-water flow ratio, and nuclear power are the average values corresponding to all monitoring channels of the gas-cooled reactor. And, the color dots corresponding to each monitoring channel will also be displayed on the page, as shown in Figure 2, the four monitoring points A, B, C, and D are marked with red, orange, yellow, and green dots on the page. Channel, each dot corresponds to a monitoring channel.
其中,在本公开实施例中,有4个监测通道时,左上角显示的氦气流量=(QA+QB+QC+QD)/4,其中,QA,QB,QC,QD分别为4个监测通道的氦水流量的实时值,即显示的氦气流量为4个监测通道的氦水流量的平均值;给水流量=(qA+qB+qC+qD)/4,其中,qA,qB,qC,qD分别为4个监测通道的给水流量的实时值,即显示的给水流量为4个监测通道的给水流量的平均值;氦水流量比=氦气流量/给水流量,即显示值为平均氦水流量比;核功率=(PA+PB+PC+PD)/4,其中,PA,PB,PC,PD分别为4个监测通道的核功率的实时值,即显示的核功率为4个监测通道的核功率的平均值,表示方式为额定核功率的百分比。Wherein, in the embodiment of the present disclosure, when there are 4 monitoring channels, the helium flow rate displayed in the upper left corner=(Q A +Q B +Q C +Q D )/4, where Q A , Q B , Q C , Q D is the real-time value of the helium water flow of the 4 monitoring channels respectively, that is, the displayed helium flow is the average value of the helium water flow of the 4 monitoring channels; the feed water flow = (q A + q B + q C + q D )/4, where q A , q B , q C , and q D are the real-time values of the feed water flow of the 4 monitoring channels respectively, that is, the displayed feed water flow is the average value of the feed water flow of the 4 monitoring channels; Flow ratio = helium flow/feed water flow, that is, the displayed value is the average helium-water flow ratio; nuclear power = (PA + P B + P C + P D ) /4, among them, PA, P B , P C , P D is the real-time value of the nuclear power of the 4 monitoring channels, that is, the displayed nuclear power is the average value of the nuclear power of the 4 monitoring channels, expressed as a percentage of the rated nuclear power.
以及,在本公开实施例中,如图2所示,页面还会显示氦水流量比上限值曲线,氦水流量比下限值曲线,以及氦水流量比理想值曲线,其中,氦水流量比上限值曲线和氦水流量比下限值曲线分别用不用颜色曲线表示,氦水流量比理想值曲线用虚线表示,氦水流量比理想值曲线是根据第三公式得到的,其中,第三公式为:y=(y1+y2)/2,基于此氦水流量比理想值曲线处于氦水流量比上限值曲线和氦水流量比下限值曲线之间,为当前氦水流量比的期望值。And, in the embodiment of the present disclosure, as shown in Figure 2, the page will also display the helium-water flow ratio upper limit curve, the helium-water flow ratio lower limit curve, and the helium-water flow ratio ideal value curve, wherein the helium water The flow ratio upper limit curve and the helium-water flow ratio lower limit curve are represented by different color curves respectively, the helium-water flow ratio ideal value curve is represented by a dotted line, and the helium-water flow ratio ideal value curve is obtained according to the third formula, wherein, The third formula is: y=(y 1 +y 2 )/2. Based on this, the ideal value curve of the helium-water flow ratio is between the upper limit curve of the helium-water flow ratio and the lower limit curve of the helium-water flow ratio, which is the current helium-water flow ratio curve. Expected value of water flow ratio.
进一步地,在气冷堆开始运行后,会计算出当前的核功率,并用竖线标识出来,此时代表各个监测通道的圆点处于当前核功率对应的氦气流量比,基于此运维人员可以直观的得出各个监测通道的氦气流量比与上限值/下限值的差距,若发现存在监测通道的氦水流量比与上限值/下限值很接近,则及时对气冷堆的流量进行调整。Furthermore, after the gas-cooled reactor starts running, the current nuclear power will be calculated and marked with a vertical line. At this time, the dots representing each monitoring channel are at the helium flow ratio corresponding to the current nuclear power. Based on this, the operation and maintenance personnel can Intuitively obtain the gap between the helium flow ratio of each monitoring channel and the upper limit/lower limit. If the helium-water flow ratio of the monitoring channel is found to be very close to the upper limit/lower limit, the flow is adjusted.
综上所述,本申请提出的高温气冷堆氦水流量的监测方法中,获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率,根据各个监测通道的氦气流量和给水流量,计算各个监测通道当前的氦水流量比,根据各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值,获取高温气冷堆对应的氦水流量比限值曲线,根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对各个监测通道进行监测。由此,本申请可以计算各个监测通道的氦水流量比,不需要依赖人工计算,以使得计算结果更加准确、直观。同时,通过氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,并基于氦水流量比的限值对各个监测通道的氦水流量比进行监测,实现了对气冷堆实时观测,从而避免高温气冷堆产生不必要停堆停机损失。In summary, in the method for monitoring the helium-water flow rate of a high-temperature gas-cooled reactor proposed in this application, the current helium flow rate, feed water flow rate, and nuclear power of each monitoring channel in a plurality of different monitoring channels are obtained, and according to the helium flow rate of each monitoring channel Flow and feed water flow, calculate the current helium-water flow ratio of each monitoring channel, calculate the current nuclear power ratio corresponding to the high-temperature gas-cooled reactor according to the nuclear power of each monitoring channel, and obtain the helium-water flow ratio limit curve corresponding to the high-temperature gas-cooled reactor , obtain the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the limit value curve of the helium-water flow ratio, and monitor each monitoring channel based on the limit value of the helium-water flow ratio. Therefore, the present application can calculate the helium-water flow ratio of each monitoring channel without relying on manual calculation, so that the calculation result is more accurate and intuitive. At the same time, the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio is obtained through the limit value curve of the helium-water flow ratio, and the helium-water flow ratio of each monitoring channel is monitored based on the limit value of the helium-water flow ratio. Real-time observation of the cold reactor, so as to avoid unnecessary shutdown losses of the high-temperature gas-cooled reactor.
实施例二Embodiment two
图3为根据本申请一个实施例提供的高温气冷堆氦水流量的监测装置的结构示意图,所述氦水流量包括氦气流量和给水流量,如图3所示,所述装置可以包括:Fig. 3 is a structural schematic diagram of a monitoring device for a high-temperature gas-cooled reactor helium water flow according to an embodiment of the present application. The helium water flow includes a helium gas flow and a feed water flow. As shown in Fig. 3, the device may include:
第一获取模块301,用于获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率;The first obtaining
第一计算模块302,用于根据各个监测通道的氦气流量和给水流量,计算各个监测通道当前的氦水流量比;The
第二计算模块303,用于根据各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值;The
第二获取模块304,用于获取高温气冷堆对应的氦水流量比限值曲线;The
监测模块305,用于根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对各个监测通道进行监测。The
综上所述,本申请提出的高温气冷堆氦水流量的监测装置中,获取多个不同监测通道中各个监测通道当前的氦气流量、给水流量和核功率,根据各个监测通道的氦气流量和给水流量,计算各个监测通道当前的氦水流量比,根据各个监测通道的核功率,计算当前高温气冷堆对应的核功率比值,获取高温气冷堆对应的氦水流量比限值曲线,根据氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,基于氦水流量比的限值对各个监测通道进行监测。由此,本申请可以计算各个监测通道的氦水流量比,不需要依赖人工计算,以使得计算结果更加准确、直观。同时,通过氦水流量比限值曲线获取当前核功率比值对应的氦水流量比的限值,并基于氦水流量比的限值对各个监测通道的氦水流量比进行监测,实现了对气冷堆实时观测,从而避免高温气冷堆产生不必要停堆停机损失。In summary, in the monitoring device for the helium-water flow rate of the high-temperature gas-cooled reactor proposed in this application, the current helium flow rate, feed water flow rate, and nuclear power of each monitoring channel in a plurality of different monitoring channels are obtained, and according to the helium flow rate of each monitoring channel Flow and feed water flow, calculate the current helium-water flow ratio of each monitoring channel, calculate the current nuclear power ratio corresponding to the high-temperature gas-cooled reactor according to the nuclear power of each monitoring channel, and obtain the helium-water flow ratio limit curve corresponding to the high-temperature gas-cooled reactor , obtain the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio according to the limit value curve of the helium-water flow ratio, and monitor each monitoring channel based on the limit value of the helium-water flow ratio. Therefore, the present application can calculate the helium-water flow ratio of each monitoring channel without relying on manual calculation, so that the calculation result is more accurate and intuitive. At the same time, the limit value of the helium-water flow ratio corresponding to the current nuclear power ratio is obtained through the limit value curve of the helium-water flow ratio, and the helium-water flow ratio of each monitoring channel is monitored based on the limit value of the helium-water flow ratio. Real-time observation of the cold reactor, so as to avoid unnecessary shutdown losses of the high-temperature gas-cooled reactor.
为了实现上述实施例,本公开还提出一种计算机存储介质。In order to realize the above-mentioned embodiments, the present disclosure also proposes a computer storage medium.
本公开实施例提供的计算机存储介质,存储有可执行程序;所述可执行程序被处理器执行后,能够实现如图1所示的方法。The computer storage medium provided by the embodiments of the present disclosure stores an executable program; after the executable program is executed by a processor, the method shown in FIG. 1 can be implemented.
为了实现上述实施例,本公开还提出一种计算机设备。In order to realize the above-mentioned embodiments, the present disclosure also proposes a computer device.
本公开实施例提供的计算机设备,包括存储器、处理器及存储在存储器上并可在处理器上运行的计算机程序;所述处理器执行所述程序时,能够实现如图1任一所示的方法。The computer equipment provided by the embodiments of the present disclosure includes a memory, a processor, and a computer program stored on the memory and operable on the processor; when the processor executes the program, it can realize any of the processes shown in Figure 1. method.
在本说明书的描述中,参考术语“一个实施例”、“一些实施例”、“示例”、“具体示例”、或“一些示例”等的描述意指结合该实施例或示例描述的具体特征、结构、材料或者特点包含于本申请的至少一个实施例或示例中。在本说明书中,对上述术语的示意性表述不必须针对的是相同的实施例或示例。而且,描述的具体特征、结构、材料或者特点可以在任一个或多个实施例或示例中以合适的方式结合。此外,在不相互矛盾的情况下,本领域的技术人员可以将本说明书中描述的不同实施例或示例以及不同实施例或示例的特征进行结合和组合。In the description of this specification, descriptions with reference to the terms "one embodiment", "some embodiments", "example", "specific examples", or "some examples" mean that specific features described in connection with the embodiment or example , structure, material or characteristic is included in at least one embodiment or example of the present application. In this specification, the schematic representations of the above terms are not necessarily directed to the same embodiment or example. Furthermore, the described specific features, structures, materials or characteristics may be combined in any suitable manner in any one or more embodiments or examples. In addition, those skilled in the art can combine and combine different embodiments or examples and features of different embodiments or examples described in this specification without conflicting with each other.
流程图中或在此以其他方式描述的任何过程或方法描述可以被理解为,表示包括一个或更多个用于实现定制逻辑功能或过程的步骤的可执行指令的代码的模块、片段或部分,并且本申请的优选实施方式的范围包括另外的实现,其中可以不按所示出或讨论的顺序,包括根据所涉及的功能按基本同时的方式或按相反的顺序,来执行功能,这应被本申请的实施例所属技术领域的技术人员所理解。Any process or method description in a flowchart or otherwise described herein may be understood to represent a module, segment or portion of code comprising one or more executable instructions for implementing a custom logical function or step of a process , and the scope of preferred embodiments of the present application includes additional implementations in which functions may be performed out of the order shown or discussed, including in substantially simultaneous fashion or in reverse order depending on the functions involved, which shall It should be understood by those skilled in the art to which the embodiments of the present application belong.
尽管上面已经示出和描述了本申请的实施例,可以理解的是,上述实施例是示例性的,不能理解为对本申请的限制,本领域的普通技术人员在本申请的范围内可以对上述实施例进行变化、修改、替换和变型。Although the embodiments of the present application have been shown and described above, it can be understood that the above embodiments are exemplary and should not be construed as limitations on the present application, and those skilled in the art can make the above-mentioned The embodiments are subject to changes, modifications, substitutions and variations.
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN116525161A (en) * | 2023-05-16 | 2023-08-01 | 华能山东石岛湾核电有限公司 | Method and system for monitoring related parameters of nuclear power of high-temperature gas cooled reactor |
| CN117393185A (en) * | 2023-08-31 | 2024-01-12 | 华能核能技术研究院有限公司 | Starting method and system of modular high-temperature gas cooled reactor unit |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4263654A (en) * | 1976-09-28 | 1981-04-21 | Hitachi, Ltd. | System for determining the normal operating value of power plant data |
| US6387819B1 (en) * | 1998-04-29 | 2002-05-14 | Applied Materials, Inc. | Method for etching low K dielectric layers |
| CN107808063A (en) * | 2017-11-22 | 2018-03-16 | 国网福建省电力有限公司 | A kind of HTGR emulation modelling method for Power System Analysis |
| CN112435768A (en) * | 2020-11-20 | 2021-03-02 | 西安热工研究院有限公司 | Method and system for controlling water supply flow of nuclear power generating unit with incremental adjusting function |
| CN113628770A (en) * | 2021-08-18 | 2021-11-09 | 上海核工程研究设计院有限公司 | Real-time monitoring system for pressure and temperature limit of nuclear power plant |
| WO2022105357A1 (en) * | 2020-11-20 | 2022-05-27 | 西安热工研究院有限公司 | Helium flow control system and method for high temperature gas-cooled reactor having incremental adjustment function |
-
2022
- 2022-09-21 CN CN202211149951.6A patent/CN115493665A/en active Pending
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4263654A (en) * | 1976-09-28 | 1981-04-21 | Hitachi, Ltd. | System for determining the normal operating value of power plant data |
| US6387819B1 (en) * | 1998-04-29 | 2002-05-14 | Applied Materials, Inc. | Method for etching low K dielectric layers |
| CN107808063A (en) * | 2017-11-22 | 2018-03-16 | 国网福建省电力有限公司 | A kind of HTGR emulation modelling method for Power System Analysis |
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