A method, system, device and medium for evaluating availability of a neutron detector
By obtaining the high-voltage characteristic curve of the neutron detector and calculating the plateau slope and voltage margin, the shortcomings of neutron detector availability assessment are solved, enabling a comprehensive assessment and lifetime prediction of the neutron detector, thus ensuring the stable operation and economy of nuclear power units.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Patents(China)
- Current Assignee / Owner
- CHINA NUCLEAR POWER ENGINEERING COMPANY LTD
- Filing Date
- 2025-06-16
- Publication Date
- 2026-06-30
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Figure CN120690474B_ABST
Abstract
Description
Technical Field
[0001] This invention relates to the field of commissioning and maintenance technology for nuclear instrumentation systems outside the nuclear power plant reactor, and in particular to a method, system, equipment and medium for assessing the availability of a neutron detector. Background Technology
[0002] The Nuclear Instrumentation System (NIS) uses neutron detectors located in measurement channels surrounding the reactor pressure vessel to measure the neutron flux level escaping the pressure vessel. This indirectly enables continuous monitoring of reactor power, power variations, and power distribution throughout the entire process from reactor startup to full-power operation. Therefore, the availability of neutron detectors during the measurement process is crucial for the stable operation and safety protection of nuclear power units.
[0003] Existing methods for assessing neutron detector availability are insufficient. They only consider the current operating status of the neutron detector and cannot guarantee that it will meet the operational requirements of the next fuel cycle. They also lack technical evaluation methods to predict the remaining service life of the neutron detector. It is possible that the detector may be operational at the beginning of a fuel cycle, but its function may deteriorate before the end of the fuel cycle. This could lead to the failure of the reactor neutron flux level monitoring function, requiring unplanned shutdown of the nuclear power unit to replace the detector, which would affect the economics of the nuclear power plant. Summary of the Invention
[0004] In view of the shortcomings of the prior art described above, the purpose of this invention is to provide a neutron detector availability assessment method, system, device and medium to solve the problems in the prior art that cannot guarantee that the neutron detector will meet the operating requirements of the next fuel cycle, and that there is a lack of technical evaluation means to predict the remaining service life of the neutron detector.
[0005] To achieve the above and other related objectives, the present invention provides a method for assessing the availability of a neutron detector, comprising: obtaining the high-pressure characteristic curve of the neutron detector in the current fuel cycle; obtaining the plateau slope of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve and the operating voltage of the neutron detector; obtaining the voltage margin of the high-pressure characteristic curve of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-pressure region voltage of the neutron detector; and determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-pressure characteristic curve.
[0006] In one embodiment of the present invention, obtaining the plateau slope of the neutron detector in the current fuel cycle based on the high-voltage characteristic curve and the operating voltage of the neutron detector includes: obtaining the plateau region of the neutron detector based on the high-voltage characteristic curve; and obtaining the plateau slope of the neutron detector in the current fuel cycle based on the plateau region and the operating voltage.
[0007] In one embodiment of the present invention, obtaining the plateau slope of the neutron detector in the current fuel cycle based on the plateau region and the operating voltage includes: obtaining a first output current value and a second output current value based on the operating voltage and a preset value; and obtaining the plateau slope of the neutron detector in the current fuel cycle based on the current output current value corresponding to the operating voltage, the first output current value, and the second output current value.
[0008] In one embodiment of the present invention, the formula for calculating the slope is: S = (I U+X -I U-X ) / I×100%; where X is a preset value, I U+X I is the first output current value corresponding to voltage U+X. U-X I represents the second output current value corresponding to voltage UX, and I represents the current output current value corresponding to voltage U.
[0009] In one embodiment of the present invention, the high-voltage characteristic curve voltage margin includes the plateau voltage margin; obtaining the high-voltage characteristic curve voltage margin of the neutron detector for the current fuel cycle based on the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-voltage region voltage of the neutron detector includes: obtaining a first conservative voltage based on the saturation current of the high-voltage characteristic curve and a first conservative parameter value; and obtaining the plateau voltage margin of the neutron detector for the current fuel cycle based on the first conservative voltage, the operating voltage, the current power level, and the upper limit of the power level to be measured by the neutron detector.
[0010] In one embodiment of the present invention, obtaining a first conservative voltage based on the saturation current of the high-voltage characteristic curve and a first conservative parameter value includes: obtaining a first conservative current based on the saturation current and the first conservative parameter value; and obtaining a first conservative voltage based on the first conservative current.
[0011] In one embodiment of the present invention, the formula for calculating the voltage margin in the plateau area is: Where V1 is the voltage margin of the plateau area, U is the operating voltage, and U a Let P be the first conservative voltage, and P be the current power level. U The upper limit of the power level required for neutron detector measurement.
[0012] In one embodiment of the present invention, the voltage margin of the high-voltage characteristic curve includes a low applied voltage margin; obtaining the voltage margin of the high-voltage characteristic curve of the neutron detector for the current fuel cycle based on the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-voltage region voltage of the neutron detector includes: obtaining a second conservative voltage based on the saturation current and the second conservative parameter value of the high-voltage characteristic curve; and obtaining the low applied voltage margin of the neutron detector for the current fuel cycle based on the second conservative voltage and the upper limit of the low-voltage region voltage.
[0013] In one embodiment of the present invention, obtaining a second conservative voltage based on the saturation current and the second conservative parameter value of the high voltage characteristic curve includes: obtaining a second conservative current based on the saturation current and the second conservative parameter value; and obtaining a second conservative voltage based on the second conservative current.
[0014] In one embodiment of the present invention, the formula for calculating the low applied voltage margin is: V2 = V0 - V b Where V2 is the low applied voltage margin, V0 is the upper limit of the low-voltage region voltage selected according to the detector type, and V b This is the second conservative voltage.
[0015] In one embodiment of the present invention, the method further includes: when the neutron detector is available, predicting the refueling overhaul replacement period of the neutron detector based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and previous fuel cycles.
[0016] In one embodiment of the present invention, the refueling overhaul period of the neutron detector is predicted based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and previous fuel cycles. This includes: predicting the voltage margin of the high-voltage characteristic curve for the next fuel cycle based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and previous fuel cycles to obtain the predicted value of the voltage margin of the high-voltage characteristic curve for the next fuel cycle; when the predicted value of the voltage margin of the high-voltage characteristic curve is less than a set value, the refueling overhaul period of the neutron detector begins after the current fuel cycle ends.
[0017] To achieve the above and other related objectives, the present invention also provides a neutron detector availability assessment system, comprising: an acquisition unit for acquiring the high-pressure characteristic curve of the neutron detector in the current fuel cycle; a plateau slope calculation unit for acquiring the plateau slope of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve; a margin calculation unit for acquiring the voltage margin of the high-pressure characteristic curve of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level required for neutron detector measurement, the operating voltage of the neutron detector, and the upper limit of the low-pressure region voltage of the neutron detector; and a determination unit for determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-pressure characteristic curve.
[0018] To achieve the above and other related objectives, the present invention provides an electronic device comprising: one or more processors; and a storage device for storing one or more programs, wherein when the one or more programs are executed by the one or more processors, the electronic device enables the aforementioned neutron detector availability assessment method.
[0019] To achieve the above and other related objectives, the present invention further provides a computer-readable storage medium having a computer program stored thereon, which, when executed by a computer processor, causes the computer to perform the aforementioned neutron detector availability assessment method.
[0020] As described above, the neutron detector availability assessment method, system, device, and medium of the present invention have the following beneficial effects: By utilizing the high-voltage characteristic curve of the neutron detector in the current fuel cycle, the plateau slope and voltage margin of the high-voltage characteristic curve in the current fuel cycle can be determined. This allows for a comprehensive assessment of the current neutron detector's availability without altering the external nuclear instrumentation system equipment. Furthermore, based on the voltage margin of the high-voltage characteristic curve of the neutron detector during the current fuel cycle and previous fuel cycles, the remaining service life of the neutron detector can be predicted. This allows for the refueling and overhaul replacement of the neutron detector before the predicted fuel cycle when it is predicted to be unavailable, providing maintenance personnel with a forward-looking prediction of the neutron detector replacement timing. This improves detector utilization while avoiding disruption to the normal operation of the nuclear power unit, thereby enhancing the unit's operational efficiency. Attached Figure Description
[0021] Figure 1 This is a flowchart illustrating the neutron detector availability assessment method provided in an embodiment of the present invention.
[0022] Figure 2 The diagram shown is a graph illustrating the relationship between the number of ions and the applied voltage, provided in an embodiment of the present invention.
[0023] Figure 3 The diagram shown is a schematic diagram of the high-voltage characteristic curve of a neutron detector provided in an embodiment of the present invention.
[0024] Figure 4 The diagram shows the high-voltage characteristic curves of neutron detectors at different power levels during the same period, as provided in an embodiment of the present invention.
[0025] Figure 5 The diagram shows high-voltage characteristic curves of a neutron detector at the same power level at different times, as provided in an embodiment of the present invention.
[0026] Figure 6 The diagram shows the low-voltage characteristic curves of a neutron detector at the same power level at different times, as provided in an embodiment of the present invention.
[0027] Figure 7 The diagram shows the trend of plateau voltage margin as a function of fuel cycle, according to an embodiment of the present invention.
[0028] Figure 8 The diagram illustrates the trend of low applied voltage margin as a function of fuel cycle according to an embodiment of the present invention.
[0029] Figure 9 The diagram shown is a structural block diagram of a neutron detector availability assessment system provided in an embodiment of the present invention.
[0030] Figure 10 The diagram shown is a structural schematic of an electronic device according to an embodiment of the present invention.
[0031] Component designation explanation
[0032] Electronic device 1; Neutron detector availability assessment system 11; Memory 12; Processor 13; Acquisition unit 111; Plateau slope calculation unit 112; Margin calculation unit 113; Determination unit 114. Detailed Implementation
[0033] The following specific examples illustrate the implementation of the present invention. Those skilled in the art can easily understand other advantages and effects of the present invention from the content disclosed in this specification. The present invention can also be implemented or applied through other different specific embodiments, and various details in this specification can also be modified or changed based on different viewpoints and applications without departing from the spirit of the present invention. It should be noted that, unless otherwise specified, the following embodiments and features described therein can be combined with each other.
[0034] It should be noted that the illustrations provided in the following embodiments are only schematic representations of the basic concept of the present invention. Therefore, the drawings only show the components related to the present invention and are not drawn according to the actual number, shape and size of the components in the actual implementation. In the actual implementation, the form, quantity and proportion of each component can be arbitrarily changed, and the layout of the components may also be more complex.
[0035] In the following description, numerous details are explored to provide a more thorough explanation of embodiments of the invention. However, it will be apparent to those skilled in the art that embodiments of the invention may be practiced without these specific details. In other embodiments, well-known structures and devices are shown in block diagram form rather than in detail to avoid obscuring embodiments of the invention.
[0036] Neutron flux refers to the number of neutrons passing through a unit area per unit time.
[0037] A neutron detector is a sensor specifically designed to detect neutrons. It converts neutron signals into electrical signals for measurement and analysis. Neutron detectors typically utilize the interaction between neutrons and the detector material to detect them. For example, some detectors use elastic or inelastic scattering of neutrons with atomic nuclei to generate secondary particles (such as protons and alpha particles). These secondary particles are detected by electrodes or other sensitive elements within the detector and converted into electrical signals.
[0038] Gas detectors are the most commonly used neutron detectors in nuclear power plants. They typically have a sealed enclosure filled with an ionizable inert gas (such as helium, nitrogen, or carbon dioxide). Inside the detector are positive and negative electrodes coated with a neutron-sensitive material (such as compounds of boron-10 or uranium-235) that readily interacts with neutrons. When a neutron interacts with the sensitive material, it produces charged particles with a certain energy, ionizing the gas inside the detector to generate electrons and positive ions. These ions drift towards the positive and negative electrodes under the influence of an applied electric field, thus generating an output signal.
[0039] Assuming N0 electron-ion pairs are formed in the detector's gas space, under the influence of an applied electric field, these electrons and positive ions move towards the positive and negative electrodes respectively, where they are collected by the electrodes, thus forming a current. For example... Figure 2 The graph shows the relationship between the number of ion pairs collected by the electrode and the applied voltage. It can be seen that when the applied voltage is at V... a and V b Between these two points, the recombination effect essentially disappears, and the initial ionization number N0 can be fully collected by the electrodes. When the reactor neutron flux level is constant, the number of collected charges remains essentially unchanged, meaning the output current of the measurement circuit remains constant; this operating region is called the saturation region.
[0040] Both intermediate-range and power-range neutron detectors in nuclear power plants operate in this saturation region. As the operating time of the neutron detector increases, factors such as the continuous consumption of its internal sensitive materials and filling gas, and the decrease in dielectric conductivity caused by physical and chemical reactions at the interface between the electrode materials and the gas, may lead to a decline in the performance of the neutron detector.
[0041] Please see Figure 1 This invention provides a method for assessing the availability of neutron detectors. By utilizing the high-pressure characteristic curve of the neutron detector during the current fuel cycle, the plateau slope and voltage margin of the high-pressure characteristic curve for the current fuel cycle can be determined. Without changing the external nuclear instrumentation system equipment, the availability of the current neutron detector can be comprehensively assessed through the plateau slope and voltage margin of the high-pressure characteristic curve, thereby ensuring the utilization rate and monitoring level of the neutron detector. This guides the maintenance of the neutron detector in daily operation and maintenance and the formulation of replacement plans, so as to avoid affecting the normal operation of the nuclear power unit due to the existence of unusable neutron detectors.
[0042] Figure 1 A flowchart illustrating a neutron detector availability assessment method according to an exemplary embodiment of this application is shown, applied to a neutron detector availability assessment system, including steps S10-S40. The following will be combined with... Figure 1 The technical solution of this application will be described in detail below.
[0043] First, step S10 is executed to obtain the high-pressure characteristic curve of the neutron detector in the current fuel cycle.
[0044] In assessing the availability of a neutron detector, a high-voltage characteristic curve can be plotted based on the detector's current fuel cycle operating status. This curve is then uploaded to the neutron detector availability assessment system. Alternatively, parameters such as the operating voltage and current output current related to the neutron detector's current fuel cycle operating status can be uploaded to the system, allowing it to plot the corresponding high-voltage characteristic curve. By acquiring this high-voltage characteristic curve, the system can further analyze the plateau variation trend and voltage margin of the high-voltage characteristic curve to determine the neutron detector's availability.
[0045] Next, step S20 is executed to obtain the plateau slope of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve and the operating voltage of the neutron detector.
[0046] After acquiring the high-pressure characteristic curve, the neutron detector availability assessment system can analyze the plateau region change trend of the high-pressure characteristic curve to determine the plateau slope change of the current fuel cycle. If the plateau slope does not meet the requirements of relevant standards, the system determines that the neutron detector is unavailable for the current fuel cycle and needs to be replaced to ensure that the neutron detector can operate in a stable plateau region.
[0047] In step S20, the plateau tilt of the neutron detector in the current fuel cycle is obtained based on the high-voltage characteristic curve and the operating voltage of the neutron detector, which may further include:
[0048] The plateau region of the neutron detector is obtained based on the high-pressure characteristic curve;
[0049] Based on the plateau region and operating voltage, the plateau inclination of the neutron detector in the current fuel cycle is obtained.
[0050] In the process of calculating the plateau slope using the high-voltage characteristic curve in the neutron detector availability assessment system, the plateau region of the neutron detector is first determined based on the high-voltage characteristic curve. This plateau region can be represented as the interval corresponding to the high-voltage characteristic curve where the output current of the neutron detector remains basically constant as the applied voltage increases. For example... Figure 2 The high-voltage characteristic curve of the neutron detector at a stable flux level is shown. It can be seen that when the applied voltage is in the range of 0–140V, the output current increases continuously with the increase of the applied voltage. After the applied voltage reaches 140V, the output current remains essentially constant with further increases in the applied voltage. The segment of the applied voltage-output current curve corresponding to this relatively constant output current is the plateau region of the high-voltage characteristic curve. After obtaining the plateau region, the availability of the neutron detector in the current fuel cycle is further determined by calculating the plateau slope at different operating voltages. This allows for timely replacement of the corresponding neutron detector after the current fuel cycle ends when the plateau slope renders the neutron detector unusable, maximizing the utilization of the neutron detector while improving the economic efficiency of nuclear power unit operation.
[0051] The process of obtaining the plateau tilt of the neutron detector during the current fuel cycle, based on the plateau region and operating voltage, may further include:
[0052] Based on the operating voltage and preset values, the first output current value and the second output current value are obtained, wherein the operating voltage corresponds to the applied voltage for normal operation of the neutron detector;
[0053] Based on the current output current value, the first output current value, and the second output current value corresponding to the operating voltage, the plateau slope of the neutron detector in the current fuel cycle is obtained.
[0054] During the neutron detector availability assessment system's calculation of the neutron detector's plateau tilt for the current fuel cycle, the plateau tilt calculation segment can be determined based on the operating voltage and preset values within the plateau region. Specifically, the first operating voltage before the current operating voltage is determined by the difference between the operating voltage and the preset value, and the second operating voltage after the current operating voltage is determined by the sum of the operating voltage and the preset value. Then, the first operating voltage is used to determine the corresponding first output current value, and the second operating voltage is used to determine the corresponding second output current value. Furthermore, the current output current value corresponding to the operating voltage is used to calculate the neutron detector's plateau tilt for the current fuel cycle. This calculated plateau tilt allows determination of whether the plateau tilt at the corresponding operating voltage meets the relevant standard requirements. If the plateau tilt at any operating voltage within the plateau region does not meet the relevant standard requirements, the corresponding neutron detector should be replaced promptly after the current fuel cycle ends. When the plateau slope corresponding to each working voltage in the plateau region meets the requirements of the relevant standards, it is determined that the plateau region change trend of the high-voltage characteristic curve of the neutron detector in the current fuel cycle meets the requirements. In addition, it is necessary to further analyze whether the voltage margin of the high-voltage characteristic curve meets the requirements to comprehensively determine whether the neutron detector is usable, and replace the neutron detector in a timely manner if it is unusable.
[0055] Furthermore, the formula for calculating the slope is: S = (I U+X -I U-X ) / I×100%; where X is a preset value, I U+X I is the first output current value corresponding to voltage U+X. U-X I represents the second output current value corresponding to voltage UX, where voltage UX is the first operating voltage, voltage U+X is the second operating voltage, and I is the current output current value corresponding to voltage U.
[0056] Assuming the minimum applied voltage in the current plateau area is 140V, and the neutron detector's operating voltage U is 600V, if the preset value X is 100V, then the first operating voltage UX is 500V, and the second operating voltage UX is 700V. Based on the first operating voltage of 500V, the first output current value I... U+X The second output current value corresponding to the second operating voltage of 700V and the current output current value I corresponding to the current operating voltage of 600V can be obtained by the formula: S = (I U+X -I U-XThe neutron detector's plateau slope S for the current fuel cycle is calculated by multiplying I by 100%. Generally, to ensure the neutron detector operates in a stable plateau region, the plateau slope S needs to be less than a certain standard value. This standard value can be adjusted depending on the type of neutron detector; for example, 4% can be selected for uranium-coated fission chambers, and 1.5% for boron-coated ionization chambers. If the plateau slope S exceeds this standard value in the high-pressure characteristic curve, it indicates that the current neutron detector is unusable and needs to be replaced after the current fuel cycle ends.
[0057] Next, step S30 is executed to obtain the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle, based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage of the neutron detector, and the upper limit of the low-pressure region voltage of the neutron detector. The high-pressure characteristic curve voltage margin may include the plateau voltage margin and the low applied voltage margin.
[0058] Please see Figure 3 , Figure 3 In one embodiment, it can be seen that when the applied voltage is in the range of 0 to 140V, the output current increases continuously with the increase of the applied voltage. This high-voltage characteristic curve segment can be represented as the low applied voltage region. When the applied voltage reaches 140V, the output current remains basically constant with the continuous increase of the applied voltage. This high-voltage characteristic curve segment where the output current remains relatively constant can be represented as the plateau region.
[0059] When analyzing the current operating status of a neutron detector using a neutron detector availability assessment system, it is necessary to consider not only the impact of the plateau region's changing trends on the neutron detector's availability, but also the impact of the voltage margin of the high-voltage characteristic curve. When considering the impact of the voltage margin of the high-voltage characteristic curve on the neutron detector's availability, on the one hand, there is a low applied voltage margin affecting the neutron detector's availability in the low applied voltage region of the high-voltage characteristic curve; on the other hand, there is a plateau region voltage margin affecting the neutron detector's availability in the plateau region. Therefore, the availability of the neutron detector can be further determined by observing the changes in the plateau region voltage margin and the low applied voltage margin.
[0060] Please see Figure 4 and Figure 5 , Figure 4 and Figure 5 In one embodiment given, Figure 4The high-voltage characteristic curves of the neutron detector at 30% FP (FP refers to reactor full power) and 100% FP power levels are shown. It can be seen that the saturation current inflection point voltage at the 30% FP power level occurs before 100V, while the saturation current inflection point voltage at the 100% FP power level occurs after 100V, meaning the saturation current inflection point voltage at the 30% FP power level is lower than that at the 100% FP power level. Therefore, it is evident that the voltage corresponding to the saturation current inflection point differs for the same neutron detector at different power levels within the same fuel cycle; that is, the inflection point voltage increases with increasing power level. Furthermore, Figure 5 The high-voltage characteristic curves of neutron detectors at the same power level at different times are shown. It can be seen that the saturation current of the high-voltage characteristic curves corresponding to the same power level is basically the same. The neutron detector's high-voltage characteristic curve has the smallest inflection point current and the largest plateau area in the first fuel cycle. The neutron detector's high-voltage characteristic curve has the second smallest inflection point current and the largest plateau area in the N+1 fuel cycle. The neutron detector's high-voltage characteristic curve has the largest inflection point current and the smallest plateau area in the 2N+1 fuel cycle. This indicates that as the number of fuel cycles increases, the neutron detector gradually ages, and the plateau area of the neutron detector's high-voltage characteristic curve gradually decreases. Therefore, the degree of aging of the neutron detector in different fuel cycles can be evaluated by the plateau voltage margin.
[0061] In step S30, when calculating the plateau voltage margin, based on the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-voltage region voltage of the neutron detector, the voltage margin of the high-voltage characteristic curve of the neutron detector for the current fuel cycle can be further included as follows:
[0062] The first conservative voltage is obtained based on the saturation current and the first conservative parameter value from the high voltage characteristic curve.
[0063] The upper limit of the power level is measured based on the first conservative voltage, the operating voltage, the current power level, and the neutron detector requirements to obtain the plateau voltage margin of the neutron detector in the current fuel cycle, wherein the operating voltage corresponds to the applied voltage for normal operation of the neutron detector.
[0064] When calculating the plateau voltage margin using a neutron detector availability assessment system, a first conservative voltage can be calculated based on the saturation current of the high-voltage characteristic curve and a set first conservative parameter value. Then, based on this first conservative voltage, the current operating voltage of the neutron detector, the current power level of the reactor, and the upper limit of the power level that the neutron detector needs to measure, the plateau voltage margin of the neutron detector for the current fuel cycle is calculated, thus determining the availability of the neutron detector. If the plateau voltage margin does not meet the corresponding requirements, the neutron detector can be directly determined to be unusable. If the plateau voltage margin meets the corresponding requirements, it is necessary to further assess the plateau tilt and the relationship between low applied voltage margin to comprehensively determine the availability of the neutron detector. This allows for a comprehensive assessment of the current neutron detector availability without changing the external nuclear instrumentation system equipment.
[0065] The first conservative voltage is obtained based on the saturation current of the high-voltage characteristic curve and the first conservative parameter value, including:
[0066] The first conservative current is obtained based on the saturation current and the value of the first conservative parameter;
[0067] The first conservative voltage is obtained based on the first conservative current.
[0068] In calculating the first conservative voltage, the first conservative current can be directly determined based on the saturation current of the high-voltage characteristic curve and the first conservative parameter value. Then, by utilizing the correspondence between the first conservative current and the high-voltage characteristic curve, the corresponding first conservative voltage can be determined.
[0069] Specifically, when the saturation current of the high-voltage characteristic curve is I sat The minimum voltage corresponding to the saturation current is U. sat When the first conservative parameter value is a, then the first conservative current I a =I sat ×a, where the first conservative voltage is the applied voltage value corresponding to the first conservative current in the high-voltage characteristic curve, and the larger the value of a, the greater the first conservative voltage U. a The more conservative the value, the better. For example, 'a' could be an empirical value of 0.9, or it could be any other value.
[0070] Furthermore, the availability of the corresponding neutron detector can be evaluated using the plateau voltage margin. The formula for calculating the plateau voltage margin is:
[0071]
[0072] Where V1 is the voltage margin of the plateau area, U is the operating voltage, and U a Let P be the first conservative voltage, and P be the current power level. UThis represents the upper limit of the power level that the neutron detector needs to measure. The reactor power level can be determined through KME thermal balance tests or other power measurement methods at the nuclear power plant. Alternatively, it can be calculated by detecting the neutron flux leaking from the reactor using a neutron detector.
[0073] When using the formula for calculating the plateau voltage margin, it is assumed that the operating voltage of the neutron detector under the current operating condition is U, and the upper limit of the required measurement power is P. U (If the range of reactor power level measured by the neutron detector can be 0–200% FP, then P) U That is, 200% FP; of course, the range at which the neutron detector measures the reactor power level can also be other ranges, P U (It could also be other values), the reactor power level at which the high-pressure characteristic curve is located, which is the current power level, is P, according to the saturation current I. sat The first conservative parameter value 'a' can be used to predetermine the corresponding first conservative voltage 'U'. a Then, the formula for calculating the voltage margin in the plateau area is used: The plateau voltage margin of the neutron detector in the current fuel cycle is calculated, and the aging degree of the corresponding neutron detector can be evaluated based on the plateau voltage margin, thereby determining its availability.
[0074] The aging of neutron detectors is affected not only by the reduced voltage margin in the plateau region but also by a rightward shift in the characteristic curve in the low applied voltage region. For example... Figure 6 It shows Figure 5 The high-voltage characteristic curves of neutron detectors at the same power level during different periods show the low-voltage characteristic curves corresponding to the 0-100V range. It can be seen that compared to the low-voltage characteristic curves of the 1st fuel cycle, the N+1th fuel cycle, and the 2N+1st fuel cycle, the low-voltage characteristic curves continuously shift to the right. The aging degree of the neutron detector can be evaluated by the low applied voltage margin corresponding to the low-voltage characteristic curves.
[0075] In step S30, when calculating the low applied voltage margin, the voltage margin of the high-voltage characteristic curve of the neutron detector for the current fuel cycle is obtained based on the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-voltage region voltage of the neutron detector. This includes:
[0076] The second conservative voltage is obtained based on the saturation current and the second conservative parameter value from the high voltage characteristic curve.
[0077] The low applied voltage margin of the neutron detector in the current fuel cycle is obtained based on the second conservative voltage and the upper limit of the low voltage zone voltage.
[0078] When calculating the low applied voltage margin using the neutron detector availability assessment system, the second conservative voltage can be calculated based on the saturation current of the high-voltage characteristic curve and the set second conservative parameter value. Then, based on this second conservative voltage and the current low-voltage upper limit of the neutron detector, the low applied voltage margin of the neutron detector for the current fuel cycle is calculated, thus determining the neutron detector's availability. If the low applied voltage margin does not meet the requirements, the neutron detector can be directly determined to be unusable. If the low applied voltage margin meets the requirements, it is necessary to further assess the plateau tilt and plateau voltage margin to comprehensively determine the neutron detector's availability. This allows for a comprehensive assessment of the current neutron detector's availability without altering the external nuclear instrumentation system equipment.
[0079] The second conservative voltage is obtained based on the saturation current and the second conservative parameter value from the high-voltage characteristic curve, including:
[0080] The second conservative current is obtained based on the saturation current and the value of the second conservative parameter.
[0081] The second conservative voltage is obtained based on the second conservative current.
[0082] In calculating the second conservative voltage, the second conservative current can be directly determined based on the saturation current and the second conservative parameter value from the high-voltage characteristic curve. Then, by utilizing the correspondence between the second conservative current and the high-voltage characteristic curve, the corresponding second conservative voltage can be determined.
[0083] Specifically, when the saturation current of the high-voltage characteristic curve is I sat The minimum voltage corresponding to the saturation current is U. sat When the second conservative parameter value is b, then the second conservative current I b =I sat ×b, where the second conservative voltage is the applied voltage value corresponding to the second conservative current in the high-voltage characteristic curve, and the larger the value of b, the greater the second conservative voltage V. b The more conservative the value, the better. For example, b could be an empirical value of 0.2, or other values.
[0084] Furthermore, the availability of a corresponding neutron detector can be evaluated by assessing its low applied voltage margin. The formula for calculating the low applied voltage margin is as follows:
[0085] V2 = V0 - V b ;
[0086] Where V2 is the second available margin, V0 is the upper limit of the low-voltage region voltage selected according to the detector type, and V b This is the second conservative voltage.
[0087] When using the formula for calculating low applied voltage margin, it is assumed that the operating voltage of the neutron detector under the current operating condition is U, and the upper limit of the required measurement power is P. U (If the range of reactor power level measured by the neutron detector can be 0–200% FP, then P) U That is, 200% FP; of course, the range at which the neutron detector measures the reactor power level can also be other ranges, P U (It could also be other values), the reactor power level at which the high-pressure characteristic curve is located, which is the current power level, is P, according to the saturation current I. sat The second conservative parameter value is b, and the corresponding second conservative voltage V can be determined in advance. b Then, using the formula for calculating low applied voltage margin: V2 = V0 - V b The low applied voltage margin of the neutron detector in the current fuel cycle is calculated, and the aging degree of the corresponding neutron detector can be evaluated based on the low applied voltage margin, thereby determining its availability.
[0088] Next, step S40 is executed to determine the availability of the neutron detector based on the voltage margin of the plateau slope and high voltage characteristic curves.
[0089] To ensure the neutron detector operates in a stable plateau region, the plateau slope of its high-voltage characteristic curve must be less than the relevant standard plateau slope threshold. This threshold varies depending on the type of neutron detector; for example, a 4% plateau slope threshold can be chosen for uranium-plated fission chambers, and a 1.5% plateau slope threshold for boron-coated ionization chambers. Other plateau slope thresholds can also be selected for uranium-plated fission chambers and boron-coated ionization chambers. After calculating the plateau slope of the neutron detector's high-voltage characteristic curve for the current fuel cycle using the neutron detector availability assessment system, if the plateau slope is less than the threshold, it indicates that the neutron detector is operating in a stable plateau region. The availability of the neutron detector can then be further determined by checking whether the voltage margin of the high-voltage characteristic curve meets the relevant requirements. Conversely, if the plateau slope is greater than or equal to the threshold, it indicates that the current neutron detector's plateau region is unstable, and the neutron detector is unusable. In this case, the neutron detector can be replaced after the current fuel cycle ends.
[0090] The voltage margin of the high-voltage characteristic curve includes the voltage margin in the plateau area and the low applied voltage margin.
[0091] When calculating the plateau voltage margin in the voltage margin of the high-voltage characteristic curve using the neutron detector availability assessment system, a smaller plateau voltage margin indicates a more severe degree of neutron aging in the detector. If the plateau voltage margin is close to the set value (such as 0, or other values), it indicates that the aging of the current fuel cycle is quite severe, and there is no sufficient plateau voltage margin to support the stable operation of the neutron detector. In this case, the neutron detector needs to be replaced.
[0092] Similarly, when the neutron detector availability assessment system calculates the low applied voltage margin in the voltage margin of the high-voltage characteristic curve, a smaller low applied voltage margin indicates a more severe degree of neutron aging in the detector. If the low applied voltage margin is close to the set value (such as 0, or other values), it indicates that the aging of the current fuel cycle is quite severe, and there is no sufficient low applied voltage margin to support the stable operation of the neutron detector. In this case, the neutron detector needs to be replaced.
[0093] Next, after step S40, that is, after determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-voltage characteristic curve, the following steps are also included:
[0094] When the neutron detector is available, the refueling and overhaul replacement period of the neutron detector is predicted based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and the previous fuel cycle.
[0095] After determining that the neutron detector is available through the neutron detector availability assessment system, the refueling and overhaul replacement period of the neutron detector can be further predicted by using the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and the previous fuel cycle. This can predict the timing of fuel cycles when the neutron detector will be unavailable, avoiding situations where the detector is still operational at the beginning of a fuel cycle, but its function deteriorates before the end of the fuel cycle, leading to unplanned shutdowns of the nuclear power unit to replace the detector and affecting the economics of the nuclear power plant.
[0096] Furthermore, based on the voltage margin of the high-voltage characteristic curves of the neutron detector in the current fuel cycle and previous fuel cycles, the refueling overhaul replacement period of the neutron detector is predicted, including:
[0097] Based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and the previous fuel cycle, the voltage margin of the high-voltage characteristic curve in the next fuel cycle is predicted to obtain the predicted value of the voltage margin of the high-voltage characteristic curve in the next fuel cycle.
[0098] When the predicted voltage margin of the high-voltage characteristic curve is less than the set value, the neutron detector will enter the refueling and overhaul replacement period after the current fuel cycle ends.
[0099] After obtaining the voltage margin of the high-voltage characteristic curve of the neutron detector for the current fuel cycle and previous fuel cycles, the neutron detector availability assessment system can use multiple voltage margins of the high-voltage characteristic curve of the neutron detector corresponding to the current fuel cycle and previous fuel cycles, and through methods such as least squares or others, to derive the trend of the voltage margin of the high-voltage characteristic curve with the fuel cycle. This allows for the prediction of the voltage margin of the high-voltage characteristic curve for the next fuel cycle. If the predicted voltage margin of the high-voltage characteristic curve is less than a set value, it indicates that the end of the current fuel cycle is a fuel cycle when the neutron detector is unusable, and the end of the current fuel cycle is designated as the refueling and overhaul replacement period for the neutron detector.
[0100] Specifically, when predicting the refueling and overhaul period of a neutron detector based on the plateau voltage margin of the neutron detector in the current fuel cycle and previous fuel cycles, multiple plateau voltage margins of the neutron detector corresponding to the current fuel cycle and previous fuel cycles can be used, for example, by least squares or other methods, to derive the trend of plateau voltage margin variation with the fuel cycle. This allows for the prediction of the plateau voltage margin value for the next fuel cycle. If the predicted plateau voltage margin value is less than a set value, it indicates that the end of the current fuel cycle is a time when the neutron detector is unusable, and the end of the current fuel cycle is taken as the refueling and overhaul period for the neutron detector.
[0101] Please see Figure 7 , Figure 7 In one embodiment, the plateau voltage margin of the neutron detector high-voltage characteristic curve for each fuel cycle can be obtained on a fuel cycle basis. Based on the fuel cycle and the plateau voltage margin, the trend of the plateau voltage margin changing with the fuel cycle can be derived. Except for the first fuel cycle, each fuel cycle of a nuclear power plant is typically around 18 months, although other time periods are also possible. By observing the trend of the plateau voltage margin changing with the fuel cycle, it is possible to predict when the neutron detector will become unusable near the end of the fuel cycle by utilizing the trend formed by the plateau voltage margin corresponding to the current fuel cycle and previous fuel cycles. Based on this, the neutron detector can be replaced during the refueling overhaul before the predicted fuel cycle arrives. This provides maintenance personnel with a forward-looking prediction of the neutron detector replacement timing, improving detector utilization while avoiding disruption to the normal operation of the nuclear power unit and improving its operational efficiency.
[0102] Similarly, when predicting the refueling and overhaul period of a neutron detector based on the low applied voltage margin of the neutron detector in the current fuel cycle and previous fuel cycles, multiple low applied voltage margins of the neutron detector corresponding to the current fuel cycle and previous fuel cycles can be used, for example, by least squares or other methods, to derive the trend of the low applied voltage margin with the fuel cycle, thereby predicting the low applied voltage margin value for the next fuel cycle. If the predicted low applied voltage margin value is less than a set value, it indicates that the end of the current fuel cycle is a fuel cycle when the neutron detector is unusable, and the end of the current fuel cycle is taken as the refueling and overhaul period for the neutron detector.
[0103] Please see Figure 8 , Figure 8 In one embodiment, the low applied voltage margin of the neutron detector high-voltage characteristic curve for each fuel cycle can be obtained on a fuel cycle basis. Based on the fuel cycle and the low applied voltage margin, the trend of the low applied voltage margin changing with the fuel cycle cycle can be obtained. Except for the first fuel cycle, each fuel cycle of a nuclear power plant is typically around 18 months, although other time periods are also possible. By observing the trend of the low applied voltage margin changing with the fuel cycle cycle, it is possible to predict the timing of fuel cycles when the neutron detector will be unusable, near the end of the fuel cycle, by utilizing the trend of the low applied voltage margin corresponding to the current fuel cycle and previous fuel cycles. Based on this, the neutron detector can be replaced during the refueling overhaul before the predicted fuel cycle arrives. This provides maintenance personnel with a forward-looking prediction of the neutron detector replacement timing, improving detector utilization while avoiding disruption to the normal operation of the nuclear power unit and improving its operational efficiency.
[0104] Please refer to 9. The present invention also provides a neutron detector availability assessment system 11, comprising: an acquisition unit 111 for acquiring the high-pressure characteristic curve of the neutron detector in the current fuel cycle; a plateau slope calculation unit 112 for acquiring the plateau slope of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve; a margin calculation unit 113 for acquiring the voltage margin of the high-pressure characteristic curve of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level required for neutron detector measurement, the operating voltage of the neutron detector, and the upper limit of the low-pressure region voltage of the neutron detector; and a determination unit 114 for determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-pressure characteristic curve.
[0105] It should be noted that the neutron detector availability assessment system 11 provided in the above embodiments and the neutron detector availability assessment method provided in the above embodiments belong to the same concept. The specific ways in which each module and unit performs its operation have been described in detail in the method embodiments, and will not be repeated here. In practical applications, the neutron detector availability assessment system 11 provided in the above embodiments can be assigned to different functional modules as needed, that is, the internal structure of the device can be divided into different functional modules to complete all or part of the functions described above. This is not a limitation here.
[0106] Please see Figure 10 The electronic device 1 may include a memory 12, a processor 13 and a bus, and may also include a computer program stored in the memory 12 and executable on the processor 13, such as a neutron detector availability assessment program.
[0107] The memory 12 includes at least one type of readable storage medium, such as flash memory, portable hard drive, multimedia card, card-type memory (e.g., SD or DX memory), magnetic memory, magnetic disk, optical disk, etc. In some embodiments, the memory 12 can be an internal storage unit of the electronic device 1, such as a portable hard drive. In other embodiments, the memory 12 can be an external storage device of the electronic device 1, such as a plug-in portable hard drive, smart media card (SMC), secure digital (SD) card, flash card, etc., equipped on the electronic device 1. Furthermore, the memory 12 can include both internal and external storage units of the electronic device 1. The memory 12 can be used not only to store application software and various types of data installed on the electronic device 1, such as code for neutron detector availability assessment, but also to temporarily store data that has been output or will be output.
[0108] In some embodiments, the processor 13 may be composed of integrated circuits, such as a single packaged integrated circuit or multiple integrated circuits with the same or different functions, including combinations of one or more central processing units (CPUs), microprocessors, digital processing chips, graphics processors, and various control chips. The processor 13 is the control unit of the electronic device 1, connecting various components of the electronic device 1 via various interfaces and lines. It executes programs or modules (such as a neutron detector availability assessment program) stored in the memory 12, and calls data stored in the memory 12 to perform various functions and process data of the electronic device 1.
[0109] The processor 13 executes the operating system of the electronic device 1 and various installed applications. The processor 13 executes the applications to implement the steps in the neutron detector availability assessment method described above.
[0110] For example, the computer program may be divided into one or more modules, which are stored in the memory 12 and executed by the processor 13 to complete this application. The one or more modules may be a series of computer program instruction segments capable of performing specific functions, which describe the execution process of the computer program in the electronic device 1. For example, the computer program may be divided into unit modules of the neutron detector availability assessment system 11.
[0111] The integrated unit implemented as a software functional module described above can be stored in a computer-readable storage medium, which can be non-volatile or volatile. The software functional module, stored in the storage medium, includes several instructions to cause a computer device (which may be a personal computer, computer equipment, or network device, etc.) or processor to execute some functions of the neutron detector availability assessment method described in the various embodiments of this application.
[0112] In summary, the neutron detector availability assessment method, system, equipment, and medium disclosed in this invention determine the plateau slope and voltage margin of the high-pressure characteristic curve of the neutron detector during the current fuel cycle by utilizing the high-pressure characteristic curve of the neutron detector. This allows for a comprehensive assessment of the current neutron detector's availability without altering the external nuclear instrumentation system equipment. Furthermore, based on the voltage margin of the high-pressure characteristic curve of the neutron detector during the current fuel cycle and previous fuel cycles, the remaining service life of the neutron detector can be predicted. This allows for the initiation of refueling and overhaul replacement of the neutron detector before the predicted fuel cycle when its unavailability is predicted, providing maintenance personnel with a forward-looking prediction of neutron detector replacement timing. This improves detector utilization while avoiding disruption to the normal operation of the nuclear power unit, thereby enhancing its operational efficiency. Therefore, this invention effectively overcomes the various shortcomings of existing technologies and possesses high industrial application value.
[0113] The above embodiments are merely illustrative of the principles and effects of the present invention and are not intended to limit the invention. Any person skilled in the art can modify or alter the above embodiments without departing from the spirit and scope of the present invention. Therefore, all equivalent modifications or alterations made by those skilled in the art without departing from the spirit and technical concept disclosed in the present invention should still be covered by the claims of the present invention.
Claims
1. A method of assessing the availability of a neutron detector, characterized by, include: Obtain the high-pressure characteristic curve of the neutron detector during the current fuel cycle; Based on the high-pressure characteristic curve and the operating voltage of the neutron detector, the plateau inclination of the neutron detector in the current fuel cycle is obtained; Based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-pressure region voltage of the neutron detector, the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle is obtained. The availability of the neutron detector is determined based on the plateau slope and the voltage margin of the high-voltage characteristic curve; The voltage margin of the high-voltage characteristic curve includes the voltage margin of the plateau region; Based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-pressure region voltage of the neutron detector, the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle is obtained, including: The first conservative voltage is obtained based on the saturation current and the first conservative parameter value of the high voltage characteristic curve. Based on the first conservative voltage, the operating voltage, the current power level, and the upper limit of the power level required for measurement by the neutron detector, the plateau voltage margin of the neutron detector for the current fuel cycle is obtained. The formula for calculating the plateau voltage margin is as follows: ; wherein, is a plateau voltage margin, is an operating voltage, is a first conservative voltage, is a current power level, is an upper limit of the power level required for the neutron detector to measure.
2. The neutron probe availability assessment method of claim 1, wherein, Based on the high-pressure characteristic curve and the operating voltage of the neutron detector, the plateau tilt of the neutron detector in the current fuel cycle is obtained, including: The plateau region of the neutron detector is obtained based on the high-pressure characteristic curve. Based on the plateau region and the operating voltage, the plateau inclination of the neutron detector in the current fuel cycle is obtained.
3. The method of claim 2, wherein, Based on the plateau region and the operating voltage, the plateau tilt of the neutron detector in the current fuel cycle is obtained, including: Based on the operating voltage and the preset value, the first output current value and the second output current value are obtained; Based on the current output current value corresponding to the operating voltage, the first output current value, and the second output current value, the plateau slope of the neutron detector in the current fuel cycle is obtained.
4. The method of claim 3, wherein, The formula for calculating the slope is: ; wherein X is a preset value, is a voltage a corresponding first output current value, is a voltage a corresponding second output current value, is a voltage a corresponding current output current value.
5. The neutron detector availability assessment method according to claim 1, characterized in that, The first conservative voltage is obtained based on the saturation current of the high-voltage characteristic curve and the first conservative parameter value, including: The first conservative current is obtained based on the saturation current and the first conservative parameter value; The first conservative voltage is obtained based on the first conservative current.
6. The neutron detector availability assessment method according to claim 1, characterized in that, The voltage margin of the high-voltage characteristic curve includes the low applied voltage margin; Based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-pressure region voltage of the neutron detector, the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle is obtained, including: The second conservative voltage is obtained based on the saturation current and the second conservative parameter value of the high voltage characteristic curve. The low applied voltage margin of the neutron detector for the current fuel cycle is obtained based on the second conservative voltage and the upper limit of the low-voltage zone voltage.
7. The neutron detector availability assessment method according to claim 6, characterized in that, Based on the saturation current and the second conservative parameter value of the high-voltage characteristic curve, the second conservative voltage is obtained, including: The second conservative current is obtained based on the saturation current and the second conservative parameter value; The second conservative voltage is obtained based on the second conservative current.
8. The neutron detector availability assessment method according to claim 6, characterized in that, The formula for calculating the low applied voltage margin is as follows: ; in, For low applied voltage margin, This is the upper limit of the low-voltage zone voltage selected based on the detector type. This is the second conservative voltage.
9. The neutron detector availability assessment method according to claim 1, characterized in that, Also includes: When the neutron detector is available, the refueling overhaul replacement period of the neutron detector is predicted based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and previous fuel cycles.
10. The neutron detector availability assessment method according to claim 9, characterized in that, Based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and previous fuel cycles, the refueling overhaul replacement period of the neutron detector is predicted, including: Based on the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle and the previous fuel cycle, the voltage margin of the high-voltage characteristic curve in the next fuel cycle is predicted to obtain the predicted value of the voltage margin of the high-voltage characteristic curve in the next fuel cycle. When the predicted voltage margin of the high-voltage characteristic curve is less than the set value, the neutron detector will enter the refueling and overhaul period after the current fuel cycle ends.
11. A neutron detector availability assessment system, characterized in that, include: The acquisition unit is used to acquire the high-pressure characteristic curve of the neutron detector in the current fuel cycle. The plateau inclination calculation unit is used to obtain the plateau inclination of the neutron detector in the current fuel cycle based on the high-pressure characteristic curve. The margin calculation unit is used to obtain the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage of the neutron detector, and the upper limit of the low-pressure voltage of the neutron detector. as well as The determination unit is used to determine the availability of the neutron detector based on the plateau slope and the voltage margin of the high-voltage characteristic curve. The voltage margin of the high-voltage characteristic curve includes the voltage margin of the plateau region; Based on the high-pressure characteristic curve, the current power level of the reactor, the upper limit of the power level to be measured by the neutron detector, the operating voltage, and the upper limit of the low-pressure region voltage of the neutron detector, the voltage margin of the high-pressure characteristic curve of the neutron detector for the current fuel cycle is obtained, including: The first conservative voltage is obtained based on the saturation current and the first conservative parameter value of the high voltage characteristic curve. Based on the first conservative voltage, the operating voltage, the current power level, and the upper limit of the power level required for measurement by the neutron detector, the plateau voltage margin of the neutron detector for the current fuel cycle is obtained. The formula for calculating the plateau voltage margin is as follows: ; in, For the voltage margin of the plateau area, Operating voltage The first conservative voltage, At the current power level, The upper limit of the power level required for neutron detector measurement.
12. An electronic device, characterized in that: The electronic device includes: One or more processors; A storage device for storing one or more programs, which, when executed by the one or more processors, cause the electronic device to implement the neutron detector availability assessment method as described in any one of claims 1 to 10.
13. A computer-readable storage medium, characterized in that, It stores a computer program that, when executed by the computer's processor, causes the computer to perform the neutron detector availability assessment method according to any one of claims 1 to 10.