WO2024040872A1 - Feasibility method and apparatus for adding repair assembly to reactor, and device - Google Patents

Abstract

A method and an apparatus for analyzing the feasibility of adding a repair assembly to a reactor, a device, a medium, and a product. The analysis method comprises: when a fuel rod in a core assembly of a reactor is damaged, replacing the damaged fuel rod with a repair rod, to obtain a repair assembly (S202); increasing power of an undamaged fuel rod adjacent to the repair rod in the repair assembly to a peak rod power of the undamaged fuel rod, placing the repair assembly that has undergone the power increase at a hottest assembly of the reactor core, and limiting an inlet flow at the hottest assembly of the reactor core to a target flow, so as to construct a target working condition (S204); constructing different reactor events in the target working condition, and calculating a departure from nucleate boiling ratio of each event (S206); separately comparing the departure from nucleate boiling ratio of each event with a target limit value, and according to a result of the comparison, determining a feasibility of normal operation of the repair assembly in the reactor (S208).

Description

Feasible methods, devices and equipment for inserting repair components in reactors

Cross-references to related applications

This application requires priority to be submitted to the China Patent Office on August 23, 2022, with the application number 2022110113180, and the application name is "Method, device and equipment for feasibility analysis of repair components in reactors", all of which are The contents are incorporated into this application by reference.

Technical field

The present application relates to a feasibility analysis method, device, computer equipment, computer-readable storage medium and computer program product for repairing components in a reactor.

Background technique

During the operation of the pressurized water reactor of a nuclear power plant, fuel rod damage may occur due to the presence of debris or operating errors. Damage to the fuel rods can cause radioactive material to leak into the coolant or increase the risk of a leak.

However, the inventor realized that the current method mainly uses damaged fuel rods to be directly replaced with stainless steel rods, but it is impossible to judge whether the core is safe after the repaired components are put into the reactor.

Contents of the invention

According to various embodiments disclosed in this application, a feasibility analysis method, device, computer equipment, computer-readable storage medium and computer program product for repairing components in a reactor are provided.

In the first aspect, this application provides a feasibility analysis method for repairing components in a reactor, including:

When the fuel rods in the core assembly of the reactor are damaged, the damaged fuel rods are replaced with repair rods to obtain the repair assembly;

Increase the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, and place the repair assembly with increased power in the reactor core at the hottest component, and limit the inlet flow rate at the hottest component of the core to the target flow rate to construct target operating conditions;

Constructing different events that occur in the reactor under the target operating conditions and calculating the deviation from nucleate boiling ratio for each of the events; and

The deviation nucleate boiling ratio of each of the events is compared with the target limit respectively, and based on the comparison results, the feasibility of the repair component operating normally in the reactor is determined.

In the second aspect, this application provides a feasibility analysis device for installing repair components in a reactor, including:

The repair module is used to replace the damaged fuel rods with repair rods to obtain repair components when the fuel rods in the reactor core assembly are damaged;

A working condition construction module for increasing the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, and increasing the power of the repair assembly Place it at the hottest component of the reactor core, and limit the inlet flow rate at the hottest component of the reactor core to the target flow rate to construct target operating conditions;

An event construction module, used to construct different events that occur in the reactor under the target operating conditions, and calculate the deviation from nucleate boiling ratio for each of the events; and

An analysis module is used to compare the deviation nucleate boiling ratio of each of the events with the target limit value, and determine the feasibility of the repair component operating normally in the reactor based on the comparison results.

In a third aspect, the present application provides a computer device, including a memory and one or more processors. Computer readable instructions are stored in the memory. When the computer readable instructions are executed by the processor, the above mentioned steps are implemented. Method steps.

In a fourth aspect, the present application provides one or more non-volatile storage media storing computer-readable instructions. When the computer-readable instructions are executed by one or more processors, the steps of the above method are implemented.

In a fifth aspect, the present application provides a computer program product, including computer-readable instructions, which are characterized in that, when the computer-readable instructions are executed by one or more processors, the steps of the above method are implemented.

Description of drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings required to be used in the embodiments will be briefly introduced below. Obviously, the drawings in the following description are only some embodiments of the present application. Those of ordinary skill in the art can also obtain other drawings based on these drawings without exerting creative efforts.

Figure 1 is an application scenario diagram of a feasibility analysis method for repairing components in a reactor according to one or more embodiments.

Figure 2 is a schematic flowchart of a method for analyzing the feasibility of installing repair components in a reactor according to one or more embodiments.

Figure 3 is a structural diagram of the position of a repair rod according to one or more embodiments.

Figure 4 is a structural diagram of another repair rod position according to one or more embodiments.

Figure 5 is a sub-channel structure diagram according to one or more embodiments.

Figure 6 is a structural diagram of another sub-channel location according to one or more embodiments.

Figure 7 is a block diagram of a device for analyzing the feasibility of installing a repair component in a reactor according to one or more embodiments.

Figure 8 is a block diagram of a computer device in accordance with one or more embodiments.

Detailed ways

In order to make the technical solutions and advantages of the present application clearer, the present application will be further described in detail below with reference to the drawings and embodiments. It should be understood that the specific embodiments described here are only used to explain the present application and are not used to limit the present application.

The method for analyzing the feasibility of repairing components in the reactor provided by this application can be applied to the application environment as shown in Figure 1. The terminal 102 and the server 104 communicate through the network. The server 104 obtains the damage status of the fuel rods in the core assembly of the reactor, and replaces the damaged fuel rods with repair rods based on the damage status of the fuel rods obtained by the server 104 . The server 104 increases the power of the undamaged fuel rod adjacent to the repair rod to the peak rod power of the undamaged fuel rod, and then places the repair component whose power is increased to the peak rod power at the location of the hottest component of the reactor core, and limits The inlet flow rate at the hottest component of the reactor core is the target flow rate to construct the target operating conditions. On the premise of the target operating conditions, the server 104 also constructs different events that occur in the reactor under the target operating conditions, and calculates the deviation from the nucleate boiling ratio for each event. The server 104 compares the calculated deviation nucleate boiling ratio of each event with the target limit value, and then determines the feasibility of the repair component operating normally in the reactor based on the comparison results. The terminal 102 can be, but is not limited to, various personal computers, laptops, smart phones, tablets, and portable wearable devices. The server 104 can be implemented as an independent server or a server cluster composed of multiple servers.

In one of the embodiments, as shown in Figure 2, a method for analyzing the feasibility of repairing components in a reactor is provided. The application of this method to the server in Figure 1 is used as an example to illustrate, including the following steps:

Step 202: When the fuel rods in the core assembly of the reactor are damaged, replace the damaged fuel rods with repair rods to obtain a repair assembly.

Among them, the reactor refers to a reactor that uses pressurized, non-boiling light water as a moderator and coolant. It consists of a fuel assembly, a moderator, a control rod assembly, a combustible poison assembly, a neutron source assembly, and a core. It is composed of a hanging basket and a pressure shell. It is a reactor type with a large number of applications and a large capacity in nuclear power plants.

The core assembly is composed of hundreds of boxless fuel assemblies with a square cross-section. The fuel assemblies are placed vertically on the grid plate under the core at a certain distance, so that the composed core is approximately cylindrical. The weight of the core The pressure shell is supported through the lower grid plate and the hanging basket of the reactor core. The size of the reactor core is determined according to the power level of the reactor and the number of fuel assemblies loaded.

The core fuel of the fuel rod is in the form of uranium dioxide ceramic pellets sintered from uranium mixture powder. The porcelain core block is a cylinder with a diameter of 1 cm and a height of 1 cm. Hundreds of pellets are stacked together and put into a slender zirconium alloy material casing with a diameter of 1 cm, a length of about 4 meters, and a thickness of about 1 mm. Because the nuclear fission reaction is like burning atoms, it is called a fuel rod.

Repair rods refer to components that can replace fuel rods when they are damaged, such as stainless steel rods. Repair components refer to components after replacing damaged fuel rods with repair rods. For example, when a fuel rod is damaged somewhere in the reactor, the damaged fuel rod needs to be replaced with a repair rod in time. The component replaced with a repair rod is called a repair component.

Specifically, when the server obtains that a fuel rod is damaged in the reactor core assembly, it needs to use a repair rod to replace the damaged fuel rod and continue to perform work in place of the damaged fuel rod so that the reactor can operate normally. Furthermore, the location of fuel rod damage can be divided into two situations: one is where the fuel rod is damaged adjacent to the guide tube, and the other is where the fuel rod is adjacent to the non-guide tube. The fuel rods were damaged.

Step 204: Increase the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, place the repair assembly with increased power at the hottest component of the reactor core, and limit The inlet flow rate at the hottest component of the reactor core is the target flow rate to construct the target operating conditions.

Among them, the undamaged fuel rods adjacent to the repair rods refer to all undamaged fuel rods directly adjacent to the repair rods. For example, in a repair assembly, if the position of the repair rod is at the edge of the repair assembly, and there are only three undamaged fuel rods directly adjacent to the repair rod, then these three undamaged fuel rods are adjacent to the repair rod position. Undamaged fuel rods. For another example, if the position of the repair rod is at the center of the repair assembly, and there are 8 undamaged fuel rods directly adjacent to the repair rod, then these 8 undamaged fuel rods are the undamaged fuel rods adjacent to the repair rod position. Great. For another example, if the position of the repair rod is adjacent to the guide tube in the repair assembly, and there are only 7 undamaged fuel rods adjacent to the position of the repair rod, then these 7 undamaged fuel rods are adjacent to the position of the repair rod. of unbroken fuel rods. After the power is increased, the undamaged fuel rod will form the hottest sub-channel inside the repair assembly. The form of the sub-channel is divided into two situations according to the location of the damaged fuel rod. Peak wand power is essentially the same as peak power, but is numerically more accurate than peak power.

The hottest component in the reactor core refers to the location of the highest power component in the reactor core. Generally speaking, the centermost component of the reactor is set to be the hottest component in the reactor. When the power of the centermost component is not the highest power component, the power of the centermost component needs to be adjusted to the highest power to ensure that the centermost component It is the hottest component of the reactor core.

Limiting the inlet flow at the hottest component of the core is achieved through a flow distribution device. The distribution of the core inlet flow can directly determine the critical heat flow density and heat pipe factor, thereby further determining the operating limits of the nuclear power plant. The critical heat flux density refers to the maximum value that the heat flux density can reach. When the maximum value is exceeded, the equipment will burn out. The heat pipe factor is the ratio of the maximum value to the average value of the quantity in the reactor core. For example, the ratio of maximum linear power density to average linear power density is the overall heat flow density heat pipe factor.

The target flow rate is the minimum flow rate required by the hottest component of the reactor core. When the reactor is working, the minimum flow rate required for operation must be achieved to avoid reactor accidents. For example, when the flow distribution is unbalanced, the power of local components will change greatly, and fuel damage accidents may occur in areas with small flow. When the flow distribution is balanced, it can be ensured that the heat generated by each component inside the core will be be taken out to avoid fuel damage.

The target operating condition refers to increasing the power of the undamaged fuel rod adjacent to the repair rod position to its peak rod power, and at the same time placing the repair component with increased power at the hottest component of the reactor core and limiting the hottest component of the core. The case where the inlet flow at the component is the target flow.

Specifically, when the power of the undamaged fuel rod adjacent to the repair rod in the repair assembly is not its peak rod power, the server adjusts to the peak rod power. When the power of the undamaged fuel rod is its peak rod power, then No power conditioning is required, and unbroken fuel rods whose power is increased to peak rod power will constitute the hottest subchannels inside the repair assembly. The repair component is then placed at the location of the hottest component of the reactor core, and the inlet flow rate at the hottest component of the reactor core is restricted to construct the target operating conditions.

Step 206: Construct different events that occur in the reactor under the target operating conditions, and calculate the deviation from nucleate boiling ratio for each event.

Among them, the different events that occur are constructed in order to obtain the deviation nucleate boiling ratio of different types of events under target operating conditions. The deviation nucleation boiling ratio is the ratio of the given deviation nucleation boiling heat flux density on the surface of the fuel element cladding to the actual heat flux density. The most important limitation limiting the thermal power output of modern pressurized water reactor cores is the minimum local deviation from the nucleate boiling ratio.

Specifically, under the target operating conditions, the server constructs different types of events that may occur in the reactor and calculates the deviation nucleation boiling ratio of each event to obtain the deviation nucleation boiling ratio of each event.

Step 208: Compare the deviation nucleate boiling ratio of each event with the target limit respectively, and determine the feasibility of the repaired component operating normally in the reactor based on the comparison results.

Among them, the target limit is the standard value used to judge whether the plan is feasible, which can be obtained through the full statistical method or the deterministic method. For example, the target limit obtained using the full statistical method is 1.35, and the target limit obtained using the deterministic method is 1.18.

Specifically, the server compares the deviation nucleate boiling ratio obtained for each constructed event with the target limit, and based on the comparison results, determines whether the repair component can operate normally in the reactor.

In a specific application, when the deviation nucleation boiling ratio obtained by calculating the tectonic event is 2.6 and the target limit is 1.35, and the deviation nucleation boiling ratio is greater than the target limit, the repair component can operate normally in the reactor. When the deviation nucleation boiling ratio obtained by calculating the tectonic event is 1.1 and the target limit is 1.35, and the deviation nucleation boiling ratio is less than the target limit, the repair component cannot operate normally in the reactor.

In the above feasibility analysis method for repair components in the reactor, by replacing the damaged fuel rods with repair rods and increasing the power of the undamaged fuel rods adjacent to the repair rods to their peak rod power, the optimal rod power can be obtained. Conservative power distribution. By placing the repaired component with increased power at the location of the hottest component of the reactor core and limiting the inlet flow at the hottest component of the reactor core, the flow through the hottest component of the reactor core can be made to be the required target traffic. Under the premise of obtaining the most conservative power distribution and limiting the inlet flow rate, different events occurring in the reactor are constructed, and the respective deviation nucleate boiling ratios of all events are calculated. By comparing the obtained deviation nucleate boiling ratios with the target limits, the feasibility of the repaired component in normal operation in the reactor can be accurately determined.

In one embodiment, when the fuel rods in the core assembly of the reactor are damaged, the damaged fuel rods are replaced with repair rods to obtain repair components, including:

Obtain the damage location where the fuel rod is damaged in the core assembly of the reactor.

After taking out the damaged fuel rod at the damaged location and placing the stainless steel rod into the damaged location, the repair component at the damaged location is determined.

Specifically, when the fuel rod is damaged in the reactor, the server first determines the location of the damaged fuel rod. After the server takes out the damaged fuel rod from the damaged location and puts the replacement stainless steel rod into the damaged location, the server can Obtain repair components that have been repaired at the damaged location.

In this embodiment, by replacing the damaged fuel rods with stainless steel rods, the safety of the operation can be improved to ensure the safe operation of the reactor, thereby avoiding deviation from nucleate boiling.

In one embodiment, the repaired component with increased power is placed at the hottest component of the reactor core, including:

Obtain the power of each component in the reactor core and determine the component with the highest power in the reactor core.

Place the repaired component with increased power at the highest power component in the reactor core.

Among them, the power of the most central component of the reactor is usually adjusted to the highest power, so that the central component is the hottest component of the core. Furthermore, when the power of the most central component of the reactor is the highest power component in the reactor, no adjustment is needed to directly determine it as the hottest component in the core. When the power of the most central component of the reactor is not the highest power component in the reactor , then the component power needs to be adjusted to the highest power so that the centermost component is the hottest component in the core.

Specifically, by obtaining the power of each component in the reactor core, the server can determine the location of the component with the highest power in the reactor core. The component with the highest power is also the hottest component. The repaired component with increased power of the undamaged fuel rod is then placed at the location of the hottest component in the core.

In this embodiment, by obtaining the power of each component of the reactor core, the component with the highest power can be determined, and then the repair component is placed at the position of the hottest component in the reactor core, so that a conservative power distribution can be obtained and the repair component can be repaired. A more accurate determination of the feasibility of normal operation in the reactor.

In one embodiment, limiting the inlet flow at the hottest component of the core to the target flow includes:

Flow profile the inlet flow of the core to limit the inlet flow at the hottest components of the core.

The target flow rate is determined based on the average flow rate under the thermal design flow rate of the reactor core.

Among them, the configuration of the inlet flow rate of the reactor core is realized through the flow distribution device. For example, when the required flow rate at the core inlet is 95% of the average flow rate at the thermal design flow rate, a flow distribution device can be used to achieve this.

The average flow under the thermal design flow is obtained by subtracting the power plant flow measurement uncertainty from the minimum measured flow. The average flow under the thermal design flow is also the minimum flow. For example, if the measured minimum flow rate is m, but there is an uncertainty factor n, which will affect the measured minimum flow value, then the value obtained by m minus n is the average flow rate under the thermal design flow rate.

The target flow represents the minimum flow required when the reactor is working, and is mainly determined by the average flow under the thermal design flow. For example, in thermal analysis, 95% of the average flow rate at the thermal design flow rate is the required target flow value.

Specifically, the server limits the core inlet traffic to the required target traffic. According to the measured minimum flow rate of the reactor core and the uncertainty factors in the power plant flow measurement, the average flow rate under the thermal design flow rate can be obtained. Then based on the obtained average flow rate under the thermal design flow rate, the value of the target flow rate is determined.

In a specific application, if the average flow under the thermal design flow is m, the required target flow is x% of the average flow under the thermal design flow, that is, the value of the target flow is the product of m and x%, and then through Flow distribution device, so that the inlet flow of the hottest components of the core for the desired target traffic. In this embodiment, by calculating the average flow rate under the thermal design flow rate, the target flow value can be determined, and then the core inlet flow rate is limited to the target flow rate, so that accurate distribution of the core inlet flow rate can be achieved.

In one embodiment, the target flow rate is determined based on the average flow rate under the thermal design flow rate of the reactor core, including:

Obtain the minimum water flow value of the reactor core and obtain the water flow value error obtained from the power plant flow measurement.

According to the minimum water flow value and error, the average flow rate under the thermal design flow rate of the reactor core is determined.

The target flow rate is determined based on the average flow rate under the thermal design flow rate of the reactor core.

Specifically, the server obtains the minimum water flow value allowed in the reactor core and the error generated during water flow measurement, and uses the difference between the minimum water flow value and the error in power plant flow measurement as the reactor core thermal design flow. average flow rate. The server obtains the specific value of the target flow rate based on the product of the flow ratio allocated by the flow distribution device to the reactor core and the average flow rate under the thermal design flow rate of the reactor core.

In embodiments, by considering errors in flow measurement in the power plant, the accuracy of the average flow rate under the thermal design flow rate of the reactor core can be improved, thereby improving the accuracy of the target flow rate.

In one embodiment, different events that occur in the reactor under the target operating conditions are constructed, and the deviation from nucleate boiling ratio of each event is calculated, including:

Construct the first event, the second event, and the third event that occur under the target operating conditions. The severity of the accidents in the first event, the second event, and the third event increases step by step.

Obtain the deviation nucleate boiling ratio in the worst case of the first event, the second event, and the third event.

Among them, the first event indicates that the reactor is operating normally without any accidents. The second event represents an event in which a minor accident occurs in the reactor, such as a loss of off-site power supply. The third event represents an event in which a serious accident occurs in the reactor, such as a rod drop accident. The deviation nucleation boiling ratio is the ratio of the given deviation nucleation boiling heat flux density on the surface of the fuel element cladding to the actual heat flux density.

Specifically, the server constructs and analyzes the first event, the second event, and the third event that may occur in the reactor core under the target operating conditions. The severity of the three types of events increases step by step, and the worst case scenario in each event is obtained. The deviation from nucleate boiling ratio.

In this embodiment, by constructing different events that occur under the target operating conditions, the deviation nucleation boiling ratios of events of different levels can be obtained. Based on the obtained deviation nucleation boiling ratios, the worst situation in each event can be determined. The deviation from nucleation boiling ratio can be achieved more accurately to determine the feasibility of the repaired component to operate normally in the reactor.

In one embodiment, obtaining the deviation nucleate boiling ratio in the worst case of each of the first event, the second event, and the third event includes:

Obtain multiple thermal and hydraulic parameters under the worst conditions of the first event, the second event, and the third event.

Based on each thermal hydraulic parameter, multiple deviation nucleate boiling ratios are obtained using a fully statistical method.

Among them, the thermal hydraulic parameters mainly include thermal power, thermal flow rate, primary side average temperature, inlet temperature, system pressure, enthalpy rise heat pipe factor and other parameters.

The full statistical method selects some representative state points covering a wide range of power level changes and pressure changes to account for the uncertainty of the critical heat flow density relationship and the differences in power plant system parameters such as power, pressure, temperature, etc. Deterministic Monte Carlo statistical sampling. After calculating the deviation from the nucleation boiling ratio for each set of sampling data, the statistical distribution of the deviation from the nucleation boiling ratio results and its standard deviation can be obtained. Then, by considering the uncertainties in the program and model, as well as the deterministic factors, the After the error, the deviation from the nucleate boiling ratio design limit under the full statistical method can be obtained.

Optionally, after the server obtains the thermal and hydraulic parameters of the first event, the second event and the third event under the worst conditions, it uses a full statistical method and uses the respective thermal and hydraulic parameters of each event to make deviation bubbles. Calculation of the nucleate boiling ratio, thereby obtaining the deviation from the nucleate boiling ratio of the first event, the second event, and the third event under the worst circumstances.

In this embodiment, by using a full statistical method to calculate the respective deviation nucleation boiling ratio of each event, the accuracy of the obtained deviation nucleation boiling ratio can be improved, thereby achieving the feasibility of normal operation of the repaired component in the reactor. Accurate judgment.

In one embodiment, the deviation nucleate boiling ratio of each event is compared with the target limit respectively, and based on the comparison results, the feasibility of normal operation of the repair component in the reactor is determined, including:

When the deviation nucleate boiling ratio of the event is greater than the target limit, it is determined that the repair component can operate normally in the reactor.

When the deviation nucleate boiling ratio of the event is less than or equal to the target limit, it is determined that the repair component cannot operate normally in the reactor.

Specifically, the server calculates the deviation from nucleate boiling ratio for each event to determine the feasibility of the repaired component operating normally in the reactor. When the worst-case deviation from nucleate boiling ratio for each event is greater than the adopted target limit, then the repair assembly can operate normally in the reactor. When the worst-case deviation from nucleate boiling ratio for each event is less than the adopted target limit, then the repair component does not operate properly in the reactor. For example, when the deviation nucleation boiling ratio obtained by calculating the tectonic event is 2.6 and the target limit is 1.35, and the deviation nucleation boiling ratio is greater than the target limit, the repair component can operate normally in the reactor. For another example, when the deviation nucleation boiling ratio obtained by calculating the worst case scenario for each event is 1.1 and the target limit is 1.35, and the deviation nucleation boiling ratio is less than the target limit, the repair component cannot operate normally in the reactor.

In this embodiment, the magnitude of the two values can be determined by comparing the worst-case deviation nucleate boiling ratio for each event with the target limit. Based on the comparison results, an accurate determination of the feasibility of the repaired component in normal operation in the reactor can be achieved.

In one embodiment, the method for analyzing the feasibility of installing repair components in the reactor also includes:

When it is determined that the repair component cannot operate normally in the reactor, a replacement order is sent.

The replacement instruction is used to instruct the update of the insertion strategy matched by the repair component, so that the updated repair component indicated by the updated insertion strategy can operate normally in the reactor.

Specifically, when the adopted strategy of repairing components into the reactor cannot make the reactor operate normally, the server will send a replacement instruction to the terminal, and the terminal will replace the matching reactor insertion strategy according to the received instruction information so that the reactor can operate normally. run.

In this embodiment, a replacement instruction is sent to instruct the replacement of the infeasible repair component insertion strategy, so that the new repair component insertion strategy can be adopted in a timely manner, thereby achieving normal operation of the reactor.

This application also provides an application scenario that applies the above-mentioned feasibility analysis method of repairing components in the reactor. Specifically, the application of the feasibility analysis method of repair components in the reactor in this application scenario is as follows: When the fuel rods in the core assembly of the reactor are damaged, the damaged fuel rods need to be replaced with repair rods. The components are called repair components. According to the location where the fuel rod is damaged, there are two main situations for replacing and repairing the rod, as shown in Figures 3 and 4. Figure 3 shows the situation where the fuel rods are damaged adjacent to the guide tube and are replaced with repair rods. Figure 4 shows the situation where the fuel rods are damaged adjacent to the non-guide tube and are replaced with repair rods. Increase the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod. The increased power fuel rod will form the hottest sub-channel inside the repair assembly, and the hottest sub-channel inside the repair assembly will be The structure of the channel is mainly divided into two situations, as shown in Figure 5 and Figure 6. Figure 5 shows the sub-channel formed after the repair rod is located adjacent to the guide tube and the fuel rod adjacent to the repair rod is heated. Figure 6 shows the sub-channel formed after the repair rod is not located adjacent to the guide tube and the fuel rod adjacent to the repair rod is heated.

Adjust the power of the central component of the reactor to the component with the highest power in the reactor core, and place the repaired component with the increased power at the position of the component with the highest power in the reactor core. The component with the highest core power is the hottest component in the core. At the same time, the inlet flow rate at the hottest component of the reactor core is limited to the target flow rate through the flow distribution device. The target flow rate is determined by the average flow rate under the thermal design. Then construct different events that occur under the target operating conditions, and calculate the deviation nucleate boiling ratio of each event based on the thermal and hydraulic parameters of each constructed event. According to the different severity levels of the events, they are divided into first events, second events and third events, and their severity increases step by step. The thermal hydraulic parameters of the worst cases in the first event, the second event and the third event are shown in Table 1, Table 2 and Table 3.

The calculated deviation nucleate boiling ratio results and target limits for each event are shown in Table 4. According to the deviation nucleation boiling ratios and target limits of the first event, the second event and the third event shown in Table 4, it can be seen that the deviation nucleation boiling ratios of the first event, the second event and the third event are larger than the deviation nucleation boiling ratio. than the target limit, that is, deviation from nucleate boiling will not occur, which means that the repaired component can operate normally in the reactor.

Table 1 Thermal hydraulic parameters of the first event

Table 2 Thermal hydraulic parameters of the second event

Table 3 Thermal hydraulic parameters of the third event

Table 4 Calculation results of deviation from nucleate boiling ratio

In one embodiment, as shown in Figure 7, a device for analyzing the feasibility of installing repair components in a reactor is provided, including:

The repair module 702 is used to replace the damaged fuel rods with repair rods when the fuel rods in the core assembly of the reactor are damaged to obtain repair components.

The working condition construction module 704 is used to increase the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, and place the repair assembly with increased power in the hottest part of the reactor core. components, and limit the inlet flow at the hottest component of the core to the target flow to construct target operating conditions.

The event construction module 706 is used to construct different events that occur in the reactor under target operating conditions, and calculate the deviation nucleate boiling ratio of each event.

The analysis module 708 is used to compare the deviation nucleate boiling ratio of each event with the target limit, and determine the feasibility of the repair component operating normally in the reactor based on the comparison results.

In one embodiment, the repair module includes:

The damage location acquisition unit is used to acquire the damage location where fuel rod damage occurs in the core assembly of the reactor.

The repair unit is used to determine the repair component of the damaged position when taking out the damaged fuel rod at the damaged position and placing the stainless steel rod into the damaged position.

In one embodiment, the working condition construction module includes:

The power acquisition unit is used to obtain the power of each component in the reactor core and determine the highest power component in the reactor core.

The component placement unit is used to place the repaired component with increased power at the component with the highest power in the reactor core.

In one embodiment, the working condition construction module includes:

The flow limiting unit is used to configure the flow rate of the inlet flow of the reactor core to limit the inlet flow rate at the hottest component of the reactor core.

The target flow rate determination unit is used to determine the target flow rate based on the average flow rate under the thermal design flow rate of the reactor core.

In one embodiment, the target traffic determining unit includes:

The data acquisition subunit is used to obtain the minimum water flow value of the reactor core and obtain the water flow value error obtained from the power plant flow measurement.

The average flow calculation subunit is used to determine the average flow under the thermal design flow of the reactor core based on the minimum water flow value and error.

The target flow rate determination subunit is used to determine the target flow rate based on the average flow rate under the thermal design flow rate of the reactor core.

In one embodiment, the event construction module includes:

The event construction unit is used to construct the first event, the second event, and the third event that occur under the target working condition. The severity of the accidents in the first event, the second event, and the third event increases step by step.

The deviation nucleation boiling ratio acquisition unit is used to acquire the deviation nucleation boiling ratio in the worst cases of each of the first event, the second event, and the third event.

In one embodiment, the deviation nucleate boiling ratio acquisition unit includes:

The thermal hydraulic parameter acquisition subunit is used to acquire multiple thermal hydraulic parameters under the worst conditions of the first event, the second event, and the third event.

The deviation nucleation boiling ratio acquisition subunit is used to obtain multiple deviation nucleation boiling ratios based on each thermal hydraulic parameter using a full statistical method.

In one embodiment, the analysis module includes:

The first determination unit is used to determine that the repair component can operate normally in the reactor when the deviation nucleate boiling ratio of the event is greater than the target limit.

The second determination unit is used to determine that the repair component cannot operate normally in the reactor when the deviation nucleate boiling ratio of the event is less than or equal to the target limit.

In one embodiment, the analysis module includes:

The instruction sending unit is used to send a replacement instruction when it is determined that the repair component cannot operate normally in the reactor.

The update unit is used for the replacement instruction to instruct the updating of the stack insertion strategy matched by the repair component, so that the updated repair component indicated by the updated stack insertion strategy can operate normally in the reactor.

For specific limitations on the device for analyzing the feasibility of installing repair components in the reactor, please refer to the limitations on the feasibility analysis method for repairing components in the reactor mentioned above, which will not be described again here. Each module in the above-mentioned reactor feasibility analysis device for repairing components in a reactor can be implemented in whole or in part by software, hardware and combinations thereof. Each of the above modules may be embedded in or independent of the processor of the computer device in the form of hardware, or may be stored in the memory of the computer device in the form of software, so that the processor can call and execute the operations corresponding to the above modules.

In one embodiment, a computer device is provided. The computer device may be a server, and its internal structure diagram may be shown in Figure 8 . The computer device includes a processor, memory, network interface, and database connected through a system bus. Wherein, the processor of the computer device is used to provide computing and control capabilities. The memory of the computer device includes non-volatile storage media and internal memory. The non-volatile storage medium stores an operating system, computer-readable instructions and a database. This internal memory provides an environment for the execution of an operating system and computer-readable instructions in a non-volatile storage medium. The database of the computer equipment is used to store fuel rod breakage in the reactor, the power of each fuel rod, each event and the deviation nucleate boiling ratio, target flow rate and target limit data for each event. The network interface of the computer device is used to communicate with external terminals through a network connection. The computer-readable instructions, when executed by the processor, implement a method for analyzing the feasibility of placing repair components in the reactor into the reactor.

Those skilled in the art can understand that the structure shown in Figure 8 is only a block diagram of a partial structure related to the solution of the present application, and does not constitute a limitation on the computer equipment to which the solution of the present application is applied. Specific computer equipment can May include more or fewer parts than shown, or combine certain parts, or have a different arrangement of parts.

In one embodiment, a computer device is provided, including a memory and one or more processors. Computer-readable instructions are stored in the memory. When the computer-readable instructions are executed by the processor, the implementation provided in any embodiment of the present application is achieved. The steps of the feasibility analysis method for repairing components in a reactor.

In one embodiment, one or more non-volatile storage media storing computer readable instructions are provided. When the computer readable instructions are executed by one or more processors, the one or more processors implement the present application. The steps of the feasibility analysis method for repairing components in a reactor provided in any embodiment.

In one embodiment, a computer program product is provided, including computer readable instructions, the computer readable instructions being processed by a processor When executed, the steps of the feasibility analysis method for repairing components in a reactor provided in any embodiment of the present application are implemented.

It should be noted that the user information (including but not limited to user equipment information, user personal information, etc.) and data (including but not limited to data used for analysis, stored data, displayed data, etc.) involved in this application are all It is information and data authorized by the user or fully authorized by all parties.

It should be understood that although the steps in the flowcharts involved in the above-mentioned embodiments are shown in sequence as indicated by the arrows, these steps are not necessarily executed in the order indicated by the arrows. Unless explicitly stated in this article, there is no strict order restriction on the execution of these steps, and these steps can be executed in other orders. Moreover, at least some of the steps in the flowcharts involved in the above embodiments may include multiple steps or stages. These steps or stages are not necessarily executed at the same time, but may be completed at different times. The execution order of these steps or stages is not necessarily sequential, but may be performed in turn or alternately with other steps or at least part of the steps or stages in other steps.

Those of ordinary skill in the art can understand that all or part of the processes in the methods of the above embodiments can be implemented by instructing relevant hardware through computer readable instructions. The computer readable instructions can be stored in a non-volatile computer. In a readable storage medium, when executed, the computer-readable instructions may include the processes of the above method embodiments. Any reference to memory, storage, database or other media used in the embodiments provided in this application may include non-volatile and/or volatile memory. Non-volatile memory may include read-only memory (ROM), programmable ROM (PROM), electrically programmable ROM (EPROM), electrically erasable programmable ROM (EEPROM), or flash memory. Volatile memory may include random access memory (RAM) or external cache memory. By way of illustration and not limitation, RAM is available in many forms, such as static RAM (SRAM), dynamic RAM (DRAM), synchronous DRAM (SDRAM), double data rate SDRAM (DDRSDRAM), enhanced SDRAM (ESDRAM), synchronous chain Synchlink DRAM (SLDRAM), memory bus (Rambus) direct RAM (RDRAM), direct memory bus dynamic RAM (DRDRAM), and memory bus dynamic RAM (RDRAM), etc.

The technical features of the above embodiments can be combined in any way. To simplify the description, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, all possible combinations should be used. It is considered to be within the scope of this manual.

The above-described embodiments only express several implementation modes of the present application, and their descriptions are relatively specific and detailed, but they should not be construed as limiting the scope of the invention patent. It should be noted that, for those of ordinary skill in the art, several modifications and improvements can be made without departing from the concept of the present application, and these all fall within the protection scope of the present application. Therefore, the protection scope of this patent application should be determined by the appended claims.

Claims (20)

1. A feasibility analysis method for repairing components in a reactor, including:

   When the fuel rods in the core assembly of the reactor are damaged, the damaged fuel rods are replaced with repair rods to obtain the repair assembly;

   Increase the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, and place the repair assembly with increased power in the reactor core at the hottest component, and limit the inlet flow rate at the hottest component of the core to the target flow rate to construct target operating conditions;

   Constructing different events that occur in the reactor under the target operating conditions and calculating the deviation from nucleate boiling ratio for each of the events; and

   The deviation nucleate boiling ratio of each of the events is compared with the target limit respectively, and based on the comparison results, the feasibility of the repair component operating normally in the reactor is determined.
2. The method according to claim 1, characterized in that when the fuel rods in the core assembly of the reactor are damaged, the damaged fuel rods are replaced with repair rods to obtain the repair assembly, which includes:

   Obtain the damage location of fuel rod damage in the core assembly of the reactor; and

   After taking out the damaged fuel rod at the damaged position and placing the stainless steel rod into the damaged position, the repair component of the damaged position is determined.
3. The method of claim 1, wherein placing the repair component with increased power at the hottest component of the reactor core includes:

   Obtain the power of each component in the reactor core and determine the highest power component in the reactor core; and

   The repair component with increased power is placed at the highest power component of the reactor core.
4. The method of claim 1, wherein limiting the inlet flow rate at the hottest component of the core to a target flow rate includes:

   Flow profile the inlet flow of the core to limit the inlet flow at the hottest components of the core; and

   The target flow rate is determined based on the average flow rate under the thermal design flow rate of the reactor core.
5. The method of claim 4, wherein determining the target flow rate based on the average flow rate under the thermal design flow rate of the reactor core includes:

   Obtain the minimum water flow value of the reactor core, and obtain the water flow value error obtained from the power plant flow measurement;

   Determine the average flow rate at the thermal design flow rate of the reactor core based on the minimum water flow value and the error; and

   The target flow rate is determined based on the average flow rate at the thermal design flow rate of the reactor core.
6. The method according to claim 1, characterized in that structuring different events that occur in the reactor under the target operating conditions and calculating the deviation nucleate boiling ratio of each event includes:

   Construct a first event, a second event, and a third event that occur under the target operating conditions; the severity levels of the first event, the second event, and the third event are gradually increased; and

   Obtain the deviation nucleate boiling ratio in the worst case of each of the first event, the second event, and the third event.
7. The method according to claim 6, characterized in that said obtaining the deviation nucleate boiling ratio in the worst case of each of the first event, the second event and the third event includes:

   Obtain multiple thermal and hydraulic parameters under the worst conditions of each of the first event, the second event, and the third event; and

   Based on each of the thermal-hydraulic parameters described, multiple deviation nucleate boiling ratios are obtained using fully statistical methods.
8. The method according to claim 1, characterized in that the deviation nucleate boiling ratio of each of the events is compared with a target limit value, and based on the comparison result, it is determined that the repair component is in the reactor. feasibility of normal operation, including:

   When the deviation from nucleate boiling ratio of the event is greater than the target limit, it is determined that the repair component can operate normally in the reactor; and

   When the deviation nucleate boiling ratio of the event is less than or equal to the target limit, it is determined that the repair component cannot operate normally in the reactor.
9. The method according to claim 1, further comprising:

   When it is determined that the repair component cannot operate normally in the reactor, a replacement instruction is sent; the replacement instruction is used to instruct the update of the stack insertion strategy matched by the repair component so that the updated stack insertion strategy indicates The updated fix component can be reacted to in the Normal operation in the heap.
10. A device for analyzing the feasibility of loading repair components in a reactor, including:

    The repair module is used to replace the damaged fuel rods with repair rods to obtain repair components when the fuel rods in the reactor core assembly are damaged;

    A working condition construction module for increasing the power of the undamaged fuel rod adjacent to the repair rod position in the repair assembly to the peak rod power of the undamaged fuel rod, and increasing the power of the repair assembly Place it at the hottest component of the reactor core, and limit the inlet flow rate at the hottest component of the reactor core to the target flow rate to construct target operating conditions;

    An event construction module, used to construct different events that occur in the reactor under the target operating conditions, and calculate the deviation from nucleate boiling ratio for each of the events; and

    An analysis module is used to compare the deviation nucleate boiling ratio of each of the events with the target limit value, and determine the feasibility of the repair component operating normally in the reactor based on the comparison results.
11. The device according to claim 10, characterized in that the repair module includes:

    The unknown damage acquisition unit is used to acquire the damage location of fuel rod damage in the core assembly of the reactor; and

    The repair unit is used to determine the repair component of the damaged position when taking out the damaged fuel rod at the damaged position and placing the stainless steel rod into the damaged position.
12. The device according to claim 10, characterized in that the working condition construction module includes:

    A power acquisition unit, used to acquire the power of each component in the reactor core and determine the highest power component in the reactor core; and

    A component placement unit is used to place the repaired component with increased power at the component with the highest power in the reactor core.
13. The device according to claim 10, characterized in that the working condition construction module includes:

    a flow limiting unit for flow configuration of the inlet flow of the reactor core to limit the inlet flow at the hottest component of the reactor core; and

    A target flow rate determining unit is configured to determine the target flow rate based on the average flow rate under the thermal design flow rate of the reactor core.
14. The device according to claim 13, characterized in that the target flow rate determination unit includes:

    A data acquisition subunit, used to obtain the minimum water flow value of the reactor core and obtain the water flow value error obtained from the power plant flow measurement;

    The average flow calculation subunit is used to determine the average flow under the thermal design flow of the reactor core based on the minimum water flow value and the error; and

    The target flow rate determination subunit is used to determine the target flow rate based on the average flow rate under the thermal design flow rate of the reactor core.
15. The device according to claim 10, characterized in that the event construction module includes:

    An event construction unit, used to construct the first event, the second event, and the third event that occur under the target operating conditions; the accident severity levels of the first event, the second event, and the third event. progressively increasing; and

    The deviation nucleation boiling ratio acquisition unit is used to acquire the deviation nucleation boiling ratio in the worst case of each of the first event, the second event, and the third event.
16. The device according to claim 15, wherein the deviation nucleate boiling ratio acquisition unit includes:

    The thermal hydraulic parameter acquisition subunit is used to acquire multiple thermal hydraulic parameters under the worst conditions of each of the first event, the second event, and the third event; and

    The deviation nucleation boiling ratio acquisition subunit is used to obtain multiple deviation nucleation boiling ratios based on each of the thermal hydraulic parameters using a full statistical method.
17. The device according to claim 10, characterized in that the analysis module includes:

    A first determination unit configured to determine that the repair component can operate normally in the reactor when the deviation from nucleate boiling ratio of the event is greater than the target limit; and

    The second determination unit is configured to determine that the repair component cannot operate normally in the reactor when the deviation from nucleate boiling ratio of the event is less than or equal to the target limit.
18. A computer device including a memory and one or more processors, with computer readable instructions stored in the memory, The computer readable instructions, when executed by the one or more processors, implement the steps of the method of any one of claims 1 to 9.
19. One or more non-volatile computer-readable storage media storing computer-readable instructions that when executed by one or more processors implement the method of any one of claims 1 to 9 A step of.
20. A computer program product comprising computer readable instructions, characterized in that, when executed by one or more processors, the computer readable instructions implement the steps of the method according to any one of claims 1 to 9.