Method and device for monitoring operation of high-temperature gas cooled reactor unit

Abstract

The invention relates to the technical field of high-temperature gas cooled reactor unit operation monitoring, and discloses a high-temperature gas cooled reactor unit operation monitoring method and a high-temperature gas cooled reactor unit operation monitoring device, which realize quick response of risk monitoring and effectively adapt to dynamic working conditions of parameter fluctuation in a transition reactor core stage through real-time judgment of a superheat degree to generate a trigger condition. Temperature and humidity information is accurately collected based on triggering conditions, stress distribution is calculated in a linkage mode, water erosion influences are simulated, vibration results are analyzed, and the multi-dimensional parameter deviation risk can be pre-judged in time. The lowest safety parameter and the control decision are determined by combining various risk results, so that the potential safety hazards such as turbine blade water erosion, vibration increase and thermal stress overrun caused by overhigh humidity of the low-pressure part of the unit can be effectively avoided, and the operation safety and stability of the high-temperature gas cooled reactor unit are remarkably improved.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of high temperature gas cooled reactor unit operation monitoring, in particular to a high temperature gas cooled reactor unit operation monitoring method and device. BACKGROUND

[0002] The high temperature gas cooled reactor nuclear power unit adopts a double reactor with a machine operation and a non-stop reactor refueling mode, and needs to go through three stages of initial installation, transition and balanced core in the operation life. In the transition core stage, the reactor power and the primary and secondary circuit parameters are lower than the design value due to the lack of fuel elements, and the steam turbine is designed based on the superheated steam working condition, which needs to strictly ensure that the inlet steam superheat degree meets the standard. Once the equipment state is abnormal and the parameters deviate, it is easy to cause the low pressure part of the steam turbine to have too high humidity, causing blade water erosion, increased vibration and other safety problems. Therefore, precise equipment state monitoring during the operation of the unit is the key to avoiding safety risks and ensuring stable operation of the unit, and has important practical significance.

[0003] Therefore, the existing high temperature gas cooled reactor nuclear power unit equipment state monitoring mostly adopts a distributed sensing monitoring scheme, which acquires operating parameters by arranging temperature, pressure and other sensors at key parts such as the reactor, steam turbine and pipeline, transmits the parameters to the monitoring center through wired transmission, and combines preset thresholds to manually analyze and judge or use a simple algorithm to give an early warning. However, the above method has a lagging monitoring response, is difficult to adapt to the dynamic working condition of parameter fluctuation in the transition core stage, cannot timely predict the risk of parameter deviation, and may further cause the low pressure part of the unit to have too high humidity, resulting in blade water erosion, increased vibration, thermal stress exceeding the limit and other safety problems of the steam turbine. SUMMARY

[0004] The present application provides a high temperature gas cooled reactor unit operation monitoring method and device to solve the problem of lagging monitoring response, difficulty in adapting to the dynamic working condition of parameter fluctuation in the transition core stage, inability to timely predict the risk of parameter deviation, and possible causes of too high humidity in the low pressure part of the unit, resulting in blade water erosion, increased vibration, thermal stress exceeding the limit and other safety problems of the steam turbine.

[0005] In a first aspect, the present application provides a high temperature gas cooled reactor unit operation monitoring method, which comprises: According to a preset water vapor temperature and pressure superheat curve, it is judged whether the current steam superheat degree is less than a preset temperature threshold, and a trigger condition is generated according to the judgment result; Based on the trigger condition, temperature information and humidity information of the high temperature gas cooled reactor unit are collected; According to the temperature information, stress distribution information of the high temperature gas cooled reactor unit is calculated; The wet steam of the humidity information is simulated to obtain a water erosion influence result on the high temperature gas cooled reactor unit, and a vibration influence result is obtained by combining the water erosion influence result and rotor vibration data; Based on the stress distribution information, the water erosion influence result and the vibration influence result, a unit minimum safety parameter and a control decision of the high-temperature gas cooled reactor unit are determined.

[0006] The application realizes rapid response of risk monitoring by generating a trigger condition through real-time determination of superheat, effectively adapts to dynamic working conditions of parameter fluctuation in the transition core stage. Based on the trigger condition, temperature and humidity information is accurately collected, stress distribution is calculated, water erosion influence is simulated, and vibration results are analyzed, which can timely predict multi-dimensional parameter deviation risks. Combined with multiple risk results, the minimum safety parameter and control decision are determined, which can effectively avoid safety hazards such as water erosion of turbine blades, increased vibration, and thermal stress exceeding limit caused by excessive humidity in the low-pressure part of the unit, and significantly improve the safety and stability of the high-temperature gas cooled reactor unit operation.

[0007] In an optional implementation, the method comprises the following steps: According to a preset water vapor temperature and pressure superheat curve, the actual temperature of the steam of the high-temperature gas cooled reactor unit and the saturation temperature under the preset pressure are obtained; The difference between the actual temperature of the steam and the saturation temperature is calculated to obtain the current steam superheat degree; It is judged whether the current steam superheat degree is less than a preset temperature threshold, and a trigger condition is generated according to the judgment result.

[0008] The application realizes accurate and real-time determination of steam superheat degree through the standardized process of temperature acquisition, difference calculation and threshold judgment. Based on the preset water vapor temperature and pressure superheat curve, the saturation temperature is obtained, the superheat degree is calculated combined with the real-time collected actual temperature of the steam, and then the trigger condition is generated through threshold comparison, which breaks through the limitation of traditional monitoring response lag, can quickly capture the superheat degree abnormality caused by parameter fluctuation in the transition core stage, and timely start the subsequent risk analysis process.

[0009] In an optional implementation, the method comprises the following steps: Based on the trigger condition, the temperature sensor and the humidity sensor of the high-temperature gas cooled reactor unit are started; The temperature information of each device of the high-temperature gas cooled reactor unit and the humidity information of the steam turbine of the high-temperature gas cooled reactor unit are collected.

[0010] The application uses the trigger condition as a pre-starting signal to realize on-demand start and stop of the temperature and humidity sensors, avoiding resource redundancy caused by invalid data collection. Accurate collection of temperature information of each device of the unit and humidity information of the steam turbine ensures the pertinence and timeliness of the data, which can quickly respond to the parameter fluctuation working condition in the transition core stage.

[0011] In an optional implementation, the calculating the stress distribution information of the high-temperature gas cooled reactor unit according to the temperature information comprises: extracting a temperature change amount of the temperature information; calculating a temperature stress value by using the temperature change amount, a preset thermal expansion coefficient and an elastic modulus of a material; determining stress distribution information based on the temperature stress value and a preset protection value.

[0012] The present application realizes accurate judgment of the stress risk of the unit by accurately extracting the temperature change amount, quantitatively calculating the temperature stress value by combining the preset thermal expansion coefficient and the elastic modulus, and determining the stress distribution information by comparing with the preset protection value.

[0013] In an optional implementation, the simulating the water erosion influence result of the wet steam of the humidity information on the high-temperature gas cooled reactor unit, and combining the water erosion influence result and rotor vibration data to obtain a vibration influence result comprises: simulating water erosion of the wet steam of the humidity information on blades and rotors of the steam turbine to obtain a water erosion influence result; collecting rotor vibration data of the rotor, and obtaining a vibration influence result according to the rotor vibration data and the water erosion influence result.

[0014] The present application constructs a linkage judgment system of water erosion-vibration risk by simulating the water erosion process of the wet steam on the blades and rotors of the steam turbine, quantitatively outputting the water erosion influence result, and simultaneously combining the rotor vibration data and the water erosion result to carry out correlation analysis to obtain the vibration influence result. The water erosion-vibration risk linkage judgment system can accurately adapt to the humidity fluctuation working condition in the transition core stage, and can timely locate the vibration abnormality source induced by water erosion.

[0015] In an optional implementation, the determining the unit lowest safety parameter and the control decision of the high-temperature gas cooled reactor unit based on the stress distribution information, the water erosion influence result and the vibration influence result comprises: determining the unit lowest safety parameter of the high-temperature gas cooled reactor unit based on the stress distribution information, the water erosion influence result and the vibration influence result; executing corresponding protection measures and control measures according to the unit lowest safety parameter and the corresponding control decision.

[0016] The present application is based on stress, water erosion, vibration multidimensional risk results, comprehensively determines the minimum safety parameters of the unit, and further combines control decision execution protection and control measures to build a closed-loop management and control system of risk research and judgment, parameter setting and measure execution. The present application precisely adapts to the dynamic working condition of parameter fluctuation in the transition core stage, solves the problems of traditional control response lag and poor parameter adaptability, can avoid safety hazards such as thermal stress overrun, blade water erosion and rotor vibration exceeding the standard from the root, and greatly improves the safety and stability of the high temperature gas cooled reactor unit operation.

[0017] In a second aspect, the present application provides a high temperature gas cooled reactor unit operation monitoring device, which comprises: A judgment module is configured to determine whether the current steam superheat degree is less than a preset temperature threshold according to a preset water vapor temperature and pressure superheat curve, and generate a trigger condition according to the determination result; A collection module is configured to collect temperature information and humidity information of the high temperature gas cooled reactor unit based on the trigger condition; A calculation module is configured to calculate stress distribution information of the high temperature gas cooled reactor unit according to the temperature information; An analog module is configured to simulate the water erosion influence result of wet steam on the high temperature gas cooled reactor unit according to the humidity information, and obtain vibration influence result in combination with the water erosion influence result and rotor vibration data; A decision module is configured to determine the minimum safety parameters and control decisions of the high temperature gas cooled reactor unit based on the stress distribution information, the water erosion influence result and the vibration influence result.

[0018] In a third aspect, the present application provides an electronic device, which comprises a memory and a processor, the memory and the processor are communicatively connected, the memory stores computer instructions, and the processor executes the computer instructions to perform the high temperature gas cooled reactor unit operation monitoring method of the first aspect or any of the corresponding embodiments thereof.

[0019] In a fourth aspect, the present application provides a computer readable storage medium, which stores computer instructions, and the computer instructions are used to make a computer execute the high temperature gas cooled reactor unit operation monitoring method of the first aspect or any of the corresponding embodiments thereof.

[0020] In a fifth aspect, the present application provides a computer program product, which comprises computer instructions, and the computer instructions are used to make a computer execute the high temperature gas cooled reactor unit operation monitoring method of the first aspect or any of the corresponding embodiments thereof. BRIEF DESCRIPTION OF DRAWINGS

[0021] To more clearly illustrate the specific embodiments of the present invention or the technical solutions in the prior art, the drawings used in the description of the specific embodiments or the prior art will be briefly introduced below. Obviously, the drawings described below are some embodiments of the present invention. For those skilled in the art, other drawings can be obtained from these drawings without creative effort.

[0022] Figure 1 This is a schematic diagram of the first process of the high-temperature gas-cooled reactor unit operation monitoring method according to an embodiment of the present invention; Figure 2 This is a schematic diagram of the second process of the high-temperature gas-cooled reactor unit operation monitoring method according to an embodiment of the present invention; Figure 3 This is a structural block diagram of a high-temperature gas-cooled reactor unit operation monitoring device according to an embodiment of the present invention; Figure 4 This is a schematic diagram of the hardware structure of an electronic device according to an embodiment of the present invention. Detailed Implementation

[0023] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions of the embodiments of the present invention will be clearly and completely described below with reference to the accompanying drawings. Obviously, the described embodiments are only some embodiments of the present invention, not all embodiments. Based on the embodiments of the present invention, all other embodiments obtained by those skilled in the art without creative effort are within the scope of protection of the present invention.

[0024] It is understood that before using the technical solutions disclosed in the various embodiments of the present invention, users should be informed of the types, scope of use, and usage scenarios of the personal information involved in the present invention and their authorization should be obtained in accordance with relevant laws and regulations through appropriate means.

[0025] This invention provides a method for monitoring the operation of a high-temperature gas-cooled reactor unit. By generating trigger conditions through real-time superheat determination, it achieves rapid response in risk monitoring and effectively adapts to the dynamic operating conditions of parameter fluctuations during the transition core stage. Based on the trigger conditions, it accurately collects temperature and humidity information, calculates stress distribution, simulates the effects of water erosion, and analyzes vibration results, enabling timely prediction of multi-dimensional parameter deviation risks. By combining multiple risk results to determine minimum safety parameters and control decisions, it can effectively avoid safety hazards such as turbine blade water erosion, increased vibration, and excessive thermal stress caused by excessive humidity in the low-pressure section of the unit, thereby significantly improving the safety and stability of the high-temperature gas-cooled reactor unit operation.

[0026] This embodiment provides a method for monitoring the operation of a high-temperature gas-cooled reactor unit. Figure 1This is a flowchart illustrating the high-temperature gas-cooled reactor unit operation monitoring method according to an embodiment of the present invention, as shown below. Figure 1 As shown, the process includes the following steps: Step S101: Based on the preset steam temperature and pressure superheat curve, determine whether the current steam superheat is less than the preset temperature threshold, and generate trigger conditions based on the determination result.

[0027] It should be noted that the preset steam temperature and pressure superheat curves refer to curves constructed in advance based on thermodynamic experimental data, which characterize the relationship between steam saturation temperature and superheat temperature under different pressures.

[0028] Current steam superheat refers to the difference between the current actual steam temperature and the saturation temperature corresponding to a specific pressure.

[0029] The preset temperature threshold refers to the minimum superheat value set based on the requirements for safe operation of the steam turbine.

[0030] Triggering conditions refer to the signal commands generated by comparing the superheat with the threshold.

[0031] In this embodiment of the invention, the saturation temperature under a specific pressure during real-time operation of the unit is obtained by matching the preset steam temperature and pressure superheat curve. Then, the current actual steam temperature at the turbine inlet of the high-temperature gas-cooled reactor unit is collected by a temperature sensor. The difference between the current actual steam temperature and the saturation temperature is calculated to obtain the current steam superheat. Subsequently, the current steam superheat is compared with a preset temperature threshold, and a valid trigger condition is generated according to the comparison result to start the subsequent temperature and humidity acquisition and risk analysis process.

[0032] Step S102: Based on the triggering conditions, collect temperature and humidity information of the high-temperature gas-cooled reactor unit.

[0033] It should be noted that a high-temperature gas-cooled reactor unit refers to a power unit that uses a high-temperature gas-cooled reactor as its heat source.

[0034] Temperature information refers to the real-time temperature data of key equipment in a high-temperature gas-cooled reactor unit, collected by temperature sensors.

[0035] Humidity information refers to data related to wet steam collected from the low-pressure section of a steam turbine, including wet steam concentration distribution and wet steam stage location.

[0036] In this embodiment of the invention, based on the triggering condition, the system immediately activates the temperature sensors deployed in key parts of the high-temperature gas-cooled reactor unit, such as the turbine cylinder, regulating stage, and shaft seal, as well as the humidity sensors used to monitor the low-pressure part of the turbine, to collect temperature information of each key device and humidity information such as the distribution of wet steam in the low-pressure part and the starting position of the wet steam stage in real time.

[0037] Step S103: Calculate the stress distribution information of the high-temperature gas-cooled reactor unit based on the temperature information.

[0038] It should be noted that stress distribution information refers to a comprehensive set of data characterizing the magnitude, distribution location, and risk level of temperature stress in each key component of a high-temperature gas-cooled reactor unit.

[0039] In this embodiment of the invention, the real-time temperature and temperature change of each key component of the high-temperature gas-cooled reactor unit are extracted from the temperature information. Combined with the preset thermal expansion coefficient and elastic modulus of the equipment material, the temperature stress value of each component is quantitatively calculated by the thermal stress calculation formula. Then, the calculated stress value is compared with the preset stress protection threshold one by one to classify the stress risk level of different components. Finally, the stress distribution information covering all key parts of the unit is integrated.

[0040] Step S104: Simulate the effect of wet steam with humidity information on water erosion of the high-temperature gas-cooled reactor unit, and combine the water erosion effect results with rotor vibration data to obtain the vibration effect results.

[0041] It should be noted that the water erosion impact results refer to the set of quantitative data obtained by simulating the wet steam erosion process, including the cumulative erosion amount of blades and rotors, the share of life loss, etc.

[0042] Rotor vibration data refers to data such as shaft amplitude, vibration frequency, and phase angle collected by vibration sensors during rotor operation.

[0043] Vibration impact results refer to the vibration risk assessment conclusions derived from dynamic analysis by combining water erosion impact results and rotor vibration data, including center of gravity offset, natural frequency change value, and risk level.

[0044] In this embodiment of the invention, the impact and wear process of wet steam droplets on blades and rotors is dynamically simulated by a preset erosion algorithm. The erosion amount is calculated cumulatively and calibrated by combining the measured data from major overhaul. The water erosion impact result, which includes the cumulative erosion amount and the life loss share, is output. Simultaneously, vibration data such as rotor shaft amplitude and vibration frequency are collected. Based on the rotor dynamics model, the center of gravity shift and natural frequency change caused by blade erosion are analyzed. Finally, the vibration risk level is determined, and the vibration impact result is formed.

[0045] Step S105: Based on stress distribution information, water erosion effect results, and vibration effect results, determine the minimum safety parameters and control decisions for the high-temperature gas-cooled reactor unit.

[0046] It should be noted that the minimum safety parameters of the unit refer to the minimum safety standards for unit operation determined by comprehensive multi-dimensional risk results, covering key parameters such as steam temperature, pressure, and unit power.

[0047] Control decisions refer to the set of operating instructions generated based on the unit's minimum safety parameters and risk levels in various dimensions, including parameter adjustments, equipment protection, and operation and maintenance recommendations.

[0048] In this embodiment of the invention, stress distribution information, water erosion impact results, and vibration impact results are extracted, including stress exceeding limits, cumulative blade erosion, rotor center of gravity offset, and vibration amplitude. The above data are compared with preset equipment safety limits one by one. Combining the parameter fluctuation characteristics and real-time operating load of the high-temperature gas-cooled reactor unit during the transition core stage, a multi-dimensional risk collaborative analysis is used to screen out the operating parameter range that can simultaneously avoid the risks of thermal stress exceeding limits, water erosion aggravation, and vibration exceeding limits. Then, the minimum safe parameters of the unit, including key indicators such as steam temperature, pressure, and unit power, are determined from this range. At the same time, control decisions covering parameter adjustment instructions, equipment protection actions, and operation and maintenance optimization suggestions are generated based on the risk levels of each dimension.

[0049] This embodiment provides a method for monitoring the operation of a high-temperature gas-cooled reactor unit. Figure 2 This is a flowchart of a high-temperature gas-cooled reactor unit operation monitoring method according to an embodiment of the present invention, such as... Figure 2 As shown, the process includes the following steps: Step S201: Based on the preset steam temperature and pressure superheat curve, determine whether the current steam superheat is less than the preset temperature threshold, and generate trigger conditions based on the determination result.

[0050] Specifically, step S201 includes: Step S2011: Based on the preset steam temperature and pressure superheat curve, obtain the current actual steam temperature and the saturation temperature under the preset pressure of the high-temperature gas-cooled reactor unit.

[0051] It should be noted that the current actual steam temperature refers to the actual temperature of the steam entering the turbine of the high-temperature gas-cooled reactor unit, which is collected in real time by a temperature sensor.

[0052] The saturation temperature under preset pressure refers to the critical temperature at which steam reaches a saturated state of gas-liquid coexistence under the real-time working pressure of the steam turbine inlet during the operation of a high-temperature gas-cooled reactor unit.

[0053] In this embodiment of the invention, a steam temperature and pressure superheat curve is pre-set. Then, a temperature sensor deployed in the steam inlet pipe of the high-temperature gas-cooled reactor unit is used to collect the actual current steam temperature entering the turbine in real time. The real-time working pressure (i.e., preset pressure) of the steam inlet of the turbine during the unit operation is obtained. Based on the preset pressure, a precise matching query is performed on the preset steam temperature and pressure superheat curve to obtain the saturation temperature at the corresponding pressure.

[0054] Step S2012: Calculate the difference between the current actual steam temperature and the saturation temperature to obtain the current steam superheat.

[0055] In this embodiment of the invention, the current steam superheat value is calculated in real time according to a preset calculation formula, thus completing the quantitative calculation of superheat. The preset calculation formula is as follows: Current steam superheat = Current actual steam temperature - Saturation temperature corresponding to a specific pressure.

[0056] Step S2013: Determine whether the current steam superheat is less than the preset temperature threshold, and generate trigger conditions based on the determination result.

[0057] It should be noted that the preset temperature threshold refers to the minimum safe limit of superheat pre-set based on the turbine's safe operation specifications, the material tolerance limits of the equipment, and the overall design parameters of the unit. In this invention, it is set to 150℃ based on the turbine's safe operation requirements.

[0058] In this embodiment of the invention, the current steam superheat value is compared with a preset temperature threshold (150°C). If the current steam superheat is less than 150°C, the triggering condition is met, a valid triggering signal is generated and transmitted to the corresponding sensor, and the unit risk analysis process is started. If the current steam superheat is greater than or equal to 150°C, the triggering condition is not met, no triggering signal is generated, and the real-time data acquisition state is maintained, and the above data acquisition, calculation and judgment process is executed in a loop.

[0059] Step S202: Based on the triggering conditions, collect temperature and humidity information of the high-temperature gas-cooled reactor unit.

[0060] In some optional implementations, step S202 above includes: Step S2021: Based on the triggering conditions, activate the temperature and humidity sensors of the high-temperature gas-cooled reactor unit.

[0061] It should be noted that temperature sensors refer to sensing devices deployed in key equipment parts of high-temperature gas-cooled reactor units (such as turbine cylinders, regulating stages, and shaft seals).

[0062] A humidity sensor is a sensing device specifically designed for the low-pressure section of a steam turbine, used to capture information such as the concentration and distribution of wet steam in real time.

[0063] In this embodiment of the invention, when the triggering condition takes effect, a start command is immediately sent to the temperature sensors deployed in key equipment parts such as the turbine cylinder, regulating stage, and shaft seal of the unit, as well as the humidity sensor configured for the low-pressure part of the turbine, so that all kinds of sensors can quickly enter the working state.

[0064] Step S2022: Collect temperature information of each piece of equipment in the high-temperature gas-cooled reactor unit and humidity information of the turbine of the high-temperature gas-cooled reactor unit.

[0065] It should be noted that the steam turbine refers to the core power component of the high-temperature gas-cooled reactor unit. It drives the generator to generate electricity by expanding steam. Its low-pressure part is prone to problems such as water erosion and vibration caused by wet steam.

[0066] In this embodiment of the invention, activated temperature sensors are used to collect real-time operating temperature data of key equipment such as the turbine cylinder, regulating stage, and shaft seals, obtaining temperature information. Real-time monitoring of these temperature parameters provides fundamental data for subsequent analysis and decision-making. Simultaneously, humidity sensors capture the inlet steam temperature and pressure of the high-pressure section of the turbine, calculating the humidity distribution in the low-pressure section to obtain humidity information and determine the starting position of the wet steam stage in the low-pressure section. Analysis of the humidity distribution helps to understand the internal working state of the turbine, providing a basis for preventing damage to the equipment from wet steam.

[0067] Step S203: Calculate the stress distribution information of the high-temperature gas-cooled reactor unit based on the temperature information.

[0068] Specifically, step S203 includes: Step S2031: Extract the temperature change information.

[0069] It should be noted that the amount of temperature change ( This refers to quantitative data formed by integrating the difference between the real-time temperature of the device and the historical reference temperature, as well as the temperature fluctuation values ​​of adjacent acquisition cycles.

[0070] In this embodiment of the invention, the amount of temperature change experienced by the structure is determined from the temperature information. .

[0071] Step S2032: Calculate the temperature stress value using the temperature change, the preset coefficient of thermal expansion, and the elastic modulus of the material.

[0072] It should be noted that the preset coefficient of thermal expansion (α) refers to the inherent physical parameters of the materials of each key component of the high-temperature gas-cooled reactor unit, which are stored in advance. Specifically, each material has its own specific coefficient of thermal expansion, which represents the amount of elongation or shrinkage per unit length of the material as a function of temperature.

[0073] The elastic modulus of a material, also known as Young's modulus, refers to a pre-defined mechanical parameter of the material, characterizing the material's ability to resist elastic deformation.

[0074] Temperature stress (σ) is a quantitative indicator calculated from temperature change, coefficient of thermal expansion, and modulus of elasticity.

[0075] In this embodiment of the invention, the stress distribution of key components of the equipment is automatically calculated based on the temperature distribution of the high-temperature gas-cooled reactor unit. The specific method for calculating the temperature stress value is as follows:

[0076] in, The change in temperature is denoted by α, which is the preset coefficient of thermal expansion. E This is the elastic modulus of the material.

[0077] Step S2033: Determine stress distribution information based on temperature stress value and preset protection value.

[0078] It should be noted that the preset protection value refers to the stress safety limit set in advance based on the material strength limit, design operation standard and safety redundancy requirements of each key equipment of the high-temperature gas-cooled reactor unit.

[0079] In this embodiment of the invention, a protection setpoint is preset, and the temperature stress value is continuously displayed via software (finite element method). When the stress of a critical component exceeds the protection setpoint, an alarm is triggered and an alarm signal is sent out so that corresponding protection and control measures can be taken in a timely manner. Specifically, the protection setpoint can be set according to different manufacturer designs or different material properties.

[0080] Step S204: Simulate the effect of wet steam with humidity information on water erosion of the high-temperature gas-cooled reactor unit, and combine the water erosion effect results with rotor vibration data to obtain the vibration effect results.

[0081] In some optional implementations, step S204 above includes: Step S2041: Simulate the water erosion of the turbine blades and rotor by wet steam with humidity information to obtain the water erosion effect results.

[0082] It should be noted that wet steam refers to steam in the low-pressure section of a steam turbine that exists in a gas-liquid coexistence state.

[0083] Water erosion refers to the phenomenon where liquid water droplets in wet steam impact the metal surfaces of turbine blades, rotors, etc., at a certain speed, causing the surface material to gradually wear off and peel off.

[0084] In this embodiment of the invention, turbine blades are modeled, and the high-speed water droplet abrasion process is simulated using software. The cumulative blade erosion over a certain power platform is calculated, and the erosion is verified using the first major overhaul time. The subsequent blade water erosion progression is predicted during unit operation. Simultaneously, the Stellite alloy thickness of the blades is input into the software, and combined with the predicted water erosion rate, when the cumulative erosion exceeds the Stellite alloy thickness (i.e., the maximum allowable water erosion), the water erosion is considered severely unacceptable. The current cumulative water erosion and the maximum allowable water erosion are used to calculate the lifetime loss share. Specifically, the calculation formula for the lifetime loss share is as follows: Life loss share = (current cumulative water erosion ÷ maximum allowable water erosion) × 100%.

[0085] By using visual simulation and calculating the percentage of life loss (water erosion percentage), the impact of water erosion on equipment lifespan can be intuitively understood, thus obtaining the results of water erosion impact. If the percentage reaches 80%, operators should be alerted that the turbine's lifespan is damaged, and it is recommended to replace the blades or carry out repairs.

[0086] Step S2042: Collect rotor vibration data and obtain vibration impact results based on rotor vibration data and water erosion impact results.

[0087] In this embodiment of the invention, high-frequency vibration sensors deployed in the rotor shaft system are linked in real time to continuously collect data such as rotor shaft amplitude, vibration frequency, and phase angle at a preset sampling frequency (e.g., 100Hz), thus obtaining rotor vibration data. Combined with the results of water erosion, and using the cumulative erosion amount and mass loss distribution of the blades caused by water erosion as the correlation basis, a rotor dynamics model analysis shows that blade erosion alters the rotor's mass balance and structural stiffness, thereby causing a shift in the center of gravity and changes in the natural frequency. The rotor vibration data is quantified and correlated with these water erosion-related effects, calculating the shift in the center of gravity and the shift in the natural frequency. The risk level is determined by comparing these values ​​with safety thresholds, ultimately forming a vibration impact result that includes the degree of vibration anomaly, the cause (water erosion correlation), and the risk level.

[0088] By monitoring and analyzing rotor vibration, potential equipment failure hazards can be detected in a timely manner. If a serious shift in the center of gravity occurs or the natural frequency approaches the turbine's operating frequency, an alarm or warning should be issued.

[0089] Step S205: Based on stress distribution information, water erosion effect results, and vibration effect results, determine the minimum safety parameters and control decisions for the high-temperature gas-cooled reactor unit.

[0090] In some optional implementations, step S205 above includes: Step S2051: Based on stress distribution information, water erosion effect results, and vibration effect results, determine the minimum safety parameters of the high-temperature gas-cooled reactor unit.

[0091] In this embodiment of the invention, stress exceedance values, cumulative blade erosion, and rotor center of gravity offset are extracted from stress distribution information, water erosion impact results, and vibration impact results, and compared with preset safety limits one by one. Combining the parameter fluctuation characteristics of the high-temperature gas-cooled reactor during the transition core stage, and integrating the unit's real-time load and core power status, a multi-objective optimization algorithm is used to screen out operating parameter ranges that can simultaneously avoid the risks of thermal stress exceedance, water erosion aggravation, and vibration exceedance. Finally, the minimum safe parameters of the unit, including key indicators such as steam temperature, pressure, and unit power, are determined from these ranges, forming a standardized parameter list.

[0092] Step S2052: Based on the unit's minimum safety parameters and the corresponding control decisions, implement the corresponding protection and control measures.

[0093] It should be noted that protective measures refer to defensive operations designed to address high-risk conditions of the unit (such as excessive stress, severe water erosion, and excessive vibration).

[0094] Control measures refer to the regulatory operations implemented to maintain the unit's operating parameters within the minimum safe range. These measures achieve stable unit operation by fine-tuning key operating indicators, including adjusting the turbine's steam inlet flow, adjusting the reactor core power, and optimizing cooling system parameters.

[0095] In this embodiment of the invention, after obtaining the unit's minimum safety parameters and the control decisions made by the operators, the parameter adjustment instructions in the decisions are first parsed and converted into executable control signals. For steam temperature and pressure parameters, precise control is achieved by adjusting the flow rate of the primary coolant loop and the opening of the secondary steam regulating valve. For unit power, the core fuel loading and unloading control logic is linked to adjust the power output to a safe range. During the control process, feedback data is collected in real time and continuously compared with the minimum safety parameters to dynamically correct the control signals, ensuring stable unit operation within the safe parameter range and avoiding secondary risks caused by parameter fluctuations.

[0096] Based on the unit's minimum safety parameters and the control decisions made by the operators, the equipment protection threshold red line is first defined. Real-time monitoring of stress, water erosion, and vibration data is conducted to check if these red lines are reached: if stress exceeds limits, protective actions such as high-pressure cylinder unloading and steam bypass depressurization are immediately triggered; if water erosion causes a lifespan loss exceeding 80%, a shutdown and maintenance warning is issued; if vibration amplitude exceeds limits, the rotor emergency braking plan is activated. Simultaneously, data from the entire protection process is recorded, and a fault analysis report is generated to provide a basis for subsequent operation and maintenance, ensuring timely protection of the equipment under risk conditions.

[0097] This invention enables real-time and comprehensive monitoring of various parameters, such as temperature, humidity, stress, and vibration, during the operation of a high-temperature gas-cooled reactor unit, providing rich data support for the unit's operational status assessment. When specific trigger conditions are met, the system automatically operates, analyzes various parameters, and promptly issues alarm signals, while simultaneously transmitting these signals to relevant modules for rapid implementation of protection and control measures, thus improving the safety and reliability of unit operation. Through a visual human-machine interface, the system intuitively presents the unit's operational status and analysis results, providing operators with clear and intuitive information to facilitate timely decision-making.

[0098] This embodiment also provides a high-temperature gas-cooled reactor unit operation monitoring device, which is used to implement the above embodiments and preferred embodiments; details already described will not be repeated. As used below, the term "module" can refer to a combination of software and / or hardware that performs a predetermined function. Although the device described in the following embodiments is preferably implemented in software, hardware implementation, or a combination of software and hardware, is also possible and contemplated.

[0099] This embodiment provides a high-temperature gas-cooled reactor unit operation monitoring device, such as... Figure 3 As shown, this device includes: The judgment module 301 is used to determine whether the current steam superheat is less than the preset temperature threshold based on the preset steam temperature and pressure superheat curve, and generate trigger conditions based on the judgment result. The acquisition module 302 is used to acquire temperature and humidity information of the high-temperature gas-cooled reactor unit based on triggering conditions; The calculation module 303 is used to calculate the stress distribution information of the high-temperature gas-cooled reactor unit based on the temperature information. Simulation module 304 is used to simulate the effect of wet steam with humidity information on water erosion of high-temperature gas-cooled reactor units, and to obtain the vibration effect results by combining the water erosion effect results with rotor vibration data; Decision module 305 is used to determine the minimum safety parameters and control decisions of the high-temperature gas-cooled reactor unit based on stress distribution information, water erosion effect results and vibration effect results.

[0100] In some optional implementations, the determination module 301 includes: The acquisition unit is used to acquire the current actual steam temperature and the saturation temperature under the preset pressure of the high-temperature gas-cooled reactor unit based on the preset steam temperature and pressure superheat curve. The first calculation unit is used to calculate the difference between the current actual steam temperature and the saturation temperature to obtain the current steam superheat. The judgment unit is used to determine whether the current steam superheat is less than the preset temperature threshold, and to generate trigger conditions based on the judgment result.

[0101] In some alternative implementations, the acquisition module 302 includes: The start-up unit is used to activate the temperature and humidity sensors of the high-temperature gas-cooled reactor unit based on triggering conditions. The data acquisition unit is used to collect temperature information of various equipment in the high-temperature gas-cooled reactor unit and humidity information of the turbine of the high-temperature gas-cooled reactor unit.

[0102] In some alternative implementations, the computing module 303 includes: The extraction unit is used to extract the temperature change information. The second calculation unit is used to calculate the temperature stress value using the temperature change, the preset thermal expansion coefficient and the elastic modulus of the material. The stress distribution unit is used to determine stress distribution information based on temperature stress values ​​and preset protection values.

[0103] In some alternative implementations, simulation module 304 includes: The water erosion unit is used to simulate the water erosion of turbine blades and rotor by wet steam with humidity information, and to obtain the results of water erosion effects. The data acquisition unit is used to acquire rotor vibration data and obtain vibration impact results based on the rotor vibration data and water erosion impact results.

[0104] In some alternative implementations, the decision module 305 includes: The safety parameter unit is used to determine the minimum safety parameters of the high-temperature gas-cooled reactor unit based on stress distribution information, water erosion effect results, and vibration effect results. The execution unit is used to execute corresponding protection and control measures based on the unit's minimum safety parameters and the corresponding control decisions.

[0105] The high-temperature gas-cooled reactor unit operation monitoring device provided in this embodiment of the invention can execute the high-temperature gas-cooled reactor unit operation monitoring method provided in any embodiment of the invention, and has the corresponding functional modules and beneficial effects for executing the method. Further functional descriptions of the above modules and units are the same as in the corresponding embodiments described above, and will not be repeated here.

[0106] Figure 4 This is a schematic diagram of the structure of an electronic device provided in an embodiment of the present invention.

[0107] The following is a detailed reference. Figure 4This diagram illustrates a structural schematic suitable for implementing an electronic device according to embodiments of the present invention. The electronic device may include a processor (e.g., a central processing unit, graphics processor, etc.) 401, which can perform various appropriate actions and processes based on a program stored in read-only memory (ROM) 402 or a program loaded from memory 408 into random access memory (RAM) 403. RAM 403 also stores various programs and data required for the operation of the electronic device. The processor 401, ROM 402, and RAM 403 are interconnected via bus 404. Input / output (I / O) interface 405 is also connected to bus 404.

[0108] Typically, the following devices can be connected to I / O interface 405: input devices 406 including, for example, touchscreens, touchpads, keyboards, mice, cameras, microphones, accelerometers, gyroscopes, etc.; output devices 407 including, for example, liquid crystal displays (LCDs), speakers, vibrators, etc.; memory devices 408 including, for example, magnetic tapes, hard disks, etc.; and communication devices 409. Communication device 409 allows electronic devices to communicate wirelessly or wiredly with other devices to exchange data. Although Figure 4 Electronic devices with various devices are shown, but it should be understood that it is not required to implement or have all of the devices shown, and more or fewer devices may be implemented or have instead.

[0109] In particular, according to embodiments of the present invention, the processes described above with reference to the flowcharts can be implemented as computer software programs. For example, embodiments of the present invention include a computer program product comprising a computer program carried on a non-transitory computer-readable medium, the computer program containing program code for performing the methods shown in the flowcharts. In such embodiments, the computer program can be downloaded and installed from a network via a communication device 409, or installed from a memory 408, or installed from a ROM 402. When the computer program is executed by the processor 401, it performs the functions defined in the high-temperature gas-cooled reactor unit operation monitoring method of the embodiments of the present invention.

[0110] Figure 4 The electronic device shown is merely an example and should not be construed as limiting the functionality and scope of the embodiments of the present invention.

[0111] This invention also provides a computer-readable storage medium. The methods described above according to embodiments of the invention can be implemented in hardware or firmware, or implemented as computer code that can be recorded on a storage medium, or implemented as computer code downloaded via a network and originally stored on a remote storage medium or a non-transitory machine-readable storage medium and then stored on a local storage medium. Thus, the methods described herein can be processed by software stored on a storage medium using a general-purpose computer, a dedicated processor, or programmable or dedicated hardware. The storage medium can be a magnetic disk, optical disk, read-only memory, random access memory, flash memory, hard disk, or solid-state drive, etc.; further, the storage medium can also include combinations of the above types of memory. It is understood that computers, processors, microprocessor controllers, or programmable hardware include storage components capable of storing or receiving software or computer code. When the software or computer code is accessed and executed by the computer, processor, or hardware, the high-temperature gas-cooled reactor unit operation monitoring method shown in the above embodiments is implemented.

[0112] A portion of this invention can be applied as a computer program product, such as computer program instructions, which, when executed by a computer, can invoke or provide the methods and / or technical solutions according to the invention through the operation of the computer. Those skilled in the art will understand that the forms in which computer program instructions exist in a computer-readable medium include, but are not limited to, source files, executable files, installation package files, etc. Correspondingly, the ways in which computer program instructions are executed by a computer include, but are not limited to: the computer directly executing the instructions, or the computer compiling the instructions and then executing the corresponding compiled program, or the computer reading and executing the instructions, or the computer reading and installing the instructions and then executing the corresponding installed program. Here, the computer-readable medium can be any available computer-readable storage medium or communication medium accessible to a computer.

[0113] Although embodiments of the invention have been described in conjunction with the accompanying drawings, those skilled in the art can make various modifications and variations without departing from the spirit and scope of the invention, and such modifications and variations all fall within the scope defined by the appended claims.

Claims

1. A method of monitoring operation of a high-temperature gas-cooled reactor plant, characterized by, The method comprises: According to the preset water vapor temperature and pressure superheating curve, it is judged whether the current steam superheat degree is less than the preset temperature threshold, and the trigger condition is generated according to the judgment result; Based on the trigger condition, the temperature information and humidity information of the high temperature gas cooled reactor unit are collected; According to the temperature information, the stress distribution information of the high temperature gas cooled reactor unit is calculated; The wet steam of the humidity information is simulated to obtain the water erosion influence result of the high temperature gas cooled reactor unit, and the vibration influence result is obtained by combining the water erosion influence result and the rotor vibration data; Based on the stress distribution information, the water erosion influence result and the vibration influence result, the lowest safety parameter and control decision of the high temperature gas cooled reactor unit are determined.

2. The method of claim 1, wherein, According to the preset water vapor temperature and pressure superheating curve, it is judged whether the current steam superheat degree is less than the preset temperature threshold, and the trigger condition is generated according to the judgment result, which comprises: According to the preset water vapor temperature and pressure superheating curve, the current steam actual temperature and the saturation temperature under the preset pressure of the high temperature gas cooled reactor unit are obtained; The difference between the current steam actual temperature and the saturation temperature is calculated to obtain the current steam superheat degree; It is judged whether the current steam superheat degree is less than the preset temperature threshold, and the trigger condition is generated according to the judgment result.

3. The method of claim 1, wherein, Based on the trigger condition, the temperature information and humidity information of the high temperature gas cooled reactor unit are collected, which comprises: Based on the trigger condition, the temperature sensor and humidity sensor of the high temperature gas cooled reactor unit are started; The temperature information of each device of the high temperature gas cooled reactor unit and the humidity information of the steam turbine of the high temperature gas cooled reactor unit are collected.

4. The method of claim 1, wherein, According to the temperature information, the stress distribution information of the high temperature gas cooled reactor unit is calculated, which comprises: The temperature change amount of the temperature information is extracted; The temperature stress value is calculated by using the temperature change amount, the preset thermal expansion coefficient and the elastic modulus of the material; Based on the temperature stress value and the preset protection value, the stress distribution information is determined.

5. The method of claim 3, wherein, The wet steam of the humidity information is simulated to obtain the water erosion influence result of the high temperature gas cooled reactor unit, and the vibration influence result is obtained by combining the water erosion influence result and the rotor vibration data, which comprises: The water erosion of the wet steam of the humidity information to the blades and rotors of the steam turbine is simulated to obtain the water erosion influence result; The rotor vibration data of the rotor are collected, and the vibration influence result is obtained according to the rotor vibration data and the water erosion influence result.

6. The method of claim 1, wherein, Based on the stress distribution information, the water erosion influence result and the vibration influence result, the lowest safety parameter and control decision of the high temperature gas cooled reactor unit are determined, which comprises: Based on the stress distribution information, the water erosion influence result and the vibration influence result, the lowest safety parameter of the high temperature gas cooled reactor unit is determined; According to the lowest safety parameter and the corresponding control decision, the corresponding protection measures and control measures are executed.

7. A device for monitoring the operation of a high-temperature gas-cooled reactor unit, characterized by The device comprises: A judgment module is configured to judge whether the current steam superheat degree is less than the preset temperature threshold according to the preset water vapor temperature and pressure superheating curve, and generate a trigger condition according to the judgment result; A collection module is configured to collect the temperature information and humidity information of the high temperature gas cooled reactor unit based on the trigger condition; A computing module is configured to calculate stress distribution information of the high-temperature gas-cooled reactor unit according to the temperature information; An analog module is configured to analogize a water erosion influence result of wet steam of the humidity information on the high-temperature gas-cooled reactor unit, and obtain a vibration influence result by combining the water erosion influence result and rotor vibration data; A decision module is configured to determine a unit lowest safety parameter and a control decision of the high-temperature gas-cooled reactor unit based on the stress distribution information, the water erosion influence result and the vibration influence result.

8. An electronic device, comprising: It comprises: A memory and a processor, which are in communication connection with each other, the memory stores computer instructions, and the processor executes the computer instructions to perform the high-temperature gas-cooled reactor unit operation monitoring method in any one of claims 1 to 6.

9. A computer-readable storage medium, characterized in that, The computer readable storage medium stores computer instructions, which are used to make the computer execute the high-temperature gas-cooled reactor unit operation monitoring method in any one of claims 1 to 6.

10. A computer program product, characterised in that, The computer instructions are used to make the computer execute the high-temperature gas-cooled reactor unit operation monitoring method in any one of claims 1 to 6.

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