Neutron detector availability evaluation method, system, equipment and medium

Abstract

The invention provides a neutron detector availability evaluation method, system, equipment and medium, and relates to the technical field of nuclear power plant ex-core nuclear instrumentation system debugging and operation and maintenance, and the evaluation method comprises the steps: obtaining a high-pressure characteristic curve of a neutron detector in a current fuel cycle period; according to the high-pressure characteristic curve, acquiring the plateau inclination of the neutron detector in the current fuel circulation period; according to the high-voltage characteristic curve, the current power level of the reactor, the power level upper limit required to be measured by the neutron detector, the working voltage of the neutron detector and the voltage upper limit of the low-voltage area of the neutron detector, obtaining the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel circulation period; and determining the availability of the neutron detector according to the plateau slope and the voltage margin of the high-voltage characteristic curve. According to the evaluation method, system, equipment and medium provided by the invention, the availability of the current neutron detector can be comprehensively evaluated and the residual service life of the neutron detector can be predicted on the premise of not changing out-of-core nuclear instrumentation system equipment.

Description

Technical Field

[0001] The present invention relates to the technical field of debugging and operation and maintenance of an off-core nuclear instrumentation system in a nuclear power plant, and in particular to a neutron detector availability assessment method, system, equipment and medium. Background Art

[0002] The Nuclear Instrumentation System (NIS) uses neutron detectors placed within the measurement channel surrounding the reactor pressure vessel to measure the neutron flux rate escaping the pressure vessel. This indirectly enables continuous monitoring of reactor power, power variations, and power distribution throughout the entire process from startup to full power operation. Therefore, the availability of neutron detectors during the measurement process is crucial to the stable operation and safety of nuclear power units.

[0003] Existing neutron detector availability assessment methods do not adequately evaluate the availability of neutron detectors. They only consider the current working status of the neutron detectors and cannot guarantee that the neutron detectors meet the operating requirements of the next fuel cycle. They also lack technical evaluation means to predict the remaining service life of neutron detectors. It is possible that the detectors can still be operated at the beginning of a fuel cycle, but the detector function deteriorates before the end of the fuel cycle, which will cause the reactor neutron flux level monitoring function to fail, requiring unplanned shutdown of the nuclear power unit to replace the detectors, affecting the economic viability of the nuclear power plant. Summary of the Invention

[0004] In view of the shortcomings of the prior art described above, the purpose of the present invention is to provide a neutron detector availability assessment method, system, equipment and medium to solve the problem that the prior art cannot ensure that the neutron detector meets the operating requirements of the next fuel cycle, and lacks technical evaluation means to predict the remaining service life of the neutron detector.

[0005] To achieve the above-mentioned and other related purposes, the present invention provides a method for evaluating the availability of a neutron detector, comprising: obtaining a high-voltage characteristic curve of the neutron detector in the current fuel cycle; obtaining a 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; obtaining a voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage, and the upper limit of the voltage in the low-voltage zone of the neutron detector; and determining the availability of the neutron detector based on the plateau slope and the voltage margin of the high-voltage characteristic curve.

[0006] In one embodiment of the present invention, the plateau slope 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, including: obtaining the plateau area of ​​the neutron detector based on the high-voltage characteristic curve; obtaining the plateau slope of the neutron detector in the current fuel cycle based on the plateau area and the operating voltage.

[0007] In one embodiment of the present invention, the plateau slope of the neutron detector in the current fuel cycle is obtained based on the plateau area and the operating voltage, including: obtaining the first output current value and the second output current value based on the operating voltage and a preset value; obtaining the plateau slope of the neutron detector in the current fuel cycle based on the current output current value, the first output current value, and the second output current value corresponding to the operating voltage.

[0008] In one embodiment of the present invention, the calculation formula of the plateau slope is: S = (I U+X -I U-X ) / I×100%; where X is the preset value, I U+X is the first output current value corresponding to the voltage U+X, I U-X is the second output current value corresponding to the voltage UX, and I is the current output current value corresponding to the voltage U.

[0009] In one embodiment of the present invention, the voltage margin of the high-voltage characteristic curve includes a plateau voltage margin; the voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage and the upper limit of the low-voltage area voltage of the neutron detector, including: obtaining the first conservative voltage based on the saturation current of the high-voltage characteristic curve and the first conservative parameter value; obtaining the plateau voltage margin of the neutron detector in 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 required to be measured by the neutron detector.

[0010] In one embodiment of the present invention, obtaining a first conservative voltage according to a saturation current and a first conservative parameter value of a high-voltage characteristic curve includes: obtaining a first conservative current according to the saturation current and the first conservative parameter value; and obtaining a first conservative voltage according to the first conservative current.

[0011] In one embodiment of the present invention, the calculation formula for the plateau voltage margin is: Among them, V1 is the voltage margin in the plateau area, U is the operating voltage, and U a is the first conservative voltage, P is the current power level, P U Upper limit of power levels measured for neutron detector requirements.

[0012] In one embodiment of the present invention, the voltage margin of the high-voltage characteristic curve includes a low external voltage margin; based on the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level required to be measured by the neutron detector, the operating voltage and the upper limit of the low-voltage zone voltage of the neutron detector, the voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle is obtained, including: obtaining the second conservative voltage based on the saturation current and the second conservative parameter value of the high-voltage characteristic curve; obtaining the low external voltage margin of the neutron detector in the current fuel cycle based on the second conservative voltage and the upper limit of the low-voltage zone voltage.

[0013] In one embodiment of the present invention, obtaining a second conservative voltage according to the saturation current and the second conservative parameter value of the high-voltage characteristic curve includes: obtaining a second conservative current according to the saturation current and the second conservative parameter value; and obtaining a second conservative voltage according to the second conservative current.

[0014] In one embodiment of the present invention, the calculation formula of the low external voltage margin is: V2 = V0 - V b ; Among them, V2 is the low external voltage margin, V0 is the upper limit of the low voltage area selected according to the detector type, V b 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 the previous fuel cycle.

[0016] In one embodiment of the present invention, the refueling overhaul and 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, including: predicting the voltage margin of the high-voltage characteristic curve of 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 the previous fuel cycle to obtain a predicted value of the voltage margin of the high-voltage characteristic curve of 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 and replacement period of the neutron detector begins after the end of the current fuel cycle.

[0017] To achieve the above-mentioned purpose and other related purposes, the present invention also provides a neutron detector availability assessment system, comprising: an acquisition unit for acquiring the high-voltage 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-voltage characteristic curve; a margin calculation unit for acquiring the voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage of the neutron detector and the upper limit of the voltage in the low-voltage zone 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-voltage characteristic curve.

[0018] To achieve the above-mentioned objectives and other related objectives, the present invention further provides an electronic device, which includes: one or more processors; a storage device for storing one or more programs, and when the one or more programs are executed by one or more processors, the electronic device implements the aforementioned neutron detector availability assessment method.

[0019] To achieve the above-mentioned and other related purposes, the present invention further provides a computer-readable storage medium having a computer program stored thereon. When the computer program is executed by a computer processor, the computer executes 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 during the current fuel cycle to determine the plateau slope and voltage margin of the high-voltage characteristic curve during the current fuel cycle, the availability of the current neutron detector can be comprehensively assessed using the plateau slope and voltage margin of the high-voltage characteristic curve without changing the equipment in the off-core nuclear instrumentation system. Furthermore, the remaining useful life of the neutron detector can be predicted based on the voltage margin of the high-voltage characteristic curve of the neutron detector during the current fuel cycle and the previous fuel cycle. Thus, when the neutron detector is predicted to be unavailable during the fuel cycle, the neutron detector can be placed into a refueling overhaul and replacement period before the predicted fuel cycle in which the neutron detector is unavailable. This provides operation and maintenance personnel with a forward-looking prediction of the timing of neutron detector replacement, thereby improving detector utilization while avoiding impacting the normal operation of the nuclear power unit and improving the operational efficiency of the nuclear power unit. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] Figure 1 A schematic flow chart of a neutron detector availability assessment method provided in an embodiment of the present invention.

[0022] Figure 2 Shown is a graph showing the relationship between the number of ion pairs and the applied voltage according to an embodiment of the present invention.

[0023] Figure 3 Shown is a schematic diagram of a high-pressure characteristic curve of a neutron detector provided by an embodiment of the present invention.

[0024] Figure 4 Shown is a schematic diagram of high-voltage characteristic curves of a neutron detector at different power levels during the same period provided by an embodiment of the present invention.

[0025] Figure 5 Schematic diagram showing high-voltage characteristic curves of a neutron detector at the same power level at different times according to an embodiment of the present invention

[0026] Figure 6 Shown is a schematic diagram of the low-voltage section characteristic curves of a neutron detector at the same power level at different times provided by an embodiment of the present invention.

[0027] Figure 7 A schematic diagram showing the variation trend of the plateau voltage margin with fuel cycles according to an embodiment of the present invention is shown.

[0028] Figure 8 Schematic diagram showing the variation trend of the low applied voltage margin with fuel cycle according to an embodiment of the present invention

[0029] Figure 9 Shown is a structural block diagram of a neutron detector availability assessment system provided by an embodiment of the present invention.

[0030] Figure 10 Shown is a structural schematic diagram of an electronic device according to an embodiment of the present invention.

[0031] Component number description

[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 DESCRIPTION

[0033] The following describes the embodiments of the present invention through specific examples. 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. The 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 the following embodiments and features in the embodiments can be combined with each other unless they conflict.

[0034] It should be noted that the illustrations provided in the following embodiments are merely schematic illustrations of the basic concept of the present invention. Therefore, the illustrations only show components related to the present invention and are not drawn according to the number, shape, and size of components in actual implementation. In actual implementation, the type, quantity, and proportion of each component may be changed arbitrarily, and the component layout may also be more complex.

[0035] In the following description, numerous details are discussed to provide a more thorough explanation of the embodiments of the present invention. However, it will be apparent to those skilled in the art that the embodiments of the present 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 the embodiments of the present invention.

[0036] Neutron flux rate 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 easy measurement and analysis. Neutron detectors typically exploit the interaction between neutrons and the detector material. For example, some detectors utilize elastic or inelastic scattering of neutrons from atomic nuclei to produce 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 consist of a sealed envelope 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 reacts readily with neutrons. When neutrons interact with the sensitive material, charged particles of a certain energy are generated, ionizing the gas inside the detector to produce electrons and positive ions. These ions drift toward the positive and negative electrodes under the influence of an applied electric field, generating an output signal.

[0039] Assuming that N0 electron-ion pairs are formed in the detector gas space, under the action of the external electric field, these electrons and positive ions move toward the positive and negative electrodes respectively and are collected by the electrodes, thus forming a current. Figure 2 The relationship between the number of ion pairs collected by the electrode and the applied voltage is shown in the figure. It can be seen that when the applied voltage is V a and V b When the neutron flux level in the reactor is constant, the number of collected charges remains essentially unchanged, that is, the output current of the measurement circuit remains unchanged. This working area is called the saturation zone.

[0040] Neutron detectors in nuclear power plants, both in the intermediate and power ranges, operate in this saturation region. As neutron detectors age, their performance may degrade due to factors such as the continued consumption of sensitive materials and filler gas, and the decrease in dielectric conductivity caused by physical and chemical reactions at the interface between electrode materials and gas.

[0041] See also Figure 1 The present invention provides a neutron detector availability assessment method. By utilizing the high-voltage characteristic curve of the neutron detector in the current fuel cycle, the plateau slope and the voltage margin of the high-voltage characteristic curve of the current fuel cycle are determined. Without changing the off-core nuclear instrument system equipment, the availability of the current neutron detector can be comprehensively assessed by using the plateau slope and the voltage margin of the high-voltage characteristic curve to ensure the utilization rate and monitoring level of the neutron detector, thereby guiding the maintenance of the neutron detector in daily operation and maintenance and formulating a replacement plan, so as to avoid affecting the normal operation of the nuclear power unit due to the existence of unavailable neutron detectors.

[0042] Figure 1 The flowchart of the neutron detector availability evaluation method in an exemplary embodiment of the present application is shown, which is applied to the neutron detector availability evaluation system, including steps S10 to S40. Figure 1 The technical solution of this application will be described in detail.

[0043] First, step S10 is executed to obtain the high-voltage characteristic curve of the neutron detector in the current fuel cycle.

[0044] In the process of evaluating the availability of a neutron detector, a corresponding high-voltage characteristic curve can be drawn based on the operating status of the neutron detector during the current fuel cycle, and then the high-voltage characteristic curve can be uploaded to the neutron detector availability assessment system. Alternatively, parameters such as the operating voltage and current output current related to the operating status of the neutron detector during the current fuel cycle can be uploaded to the neutron detector availability assessment system so that the neutron detector availability assessment system can draw the corresponding high-voltage characteristic curve, thereby enabling the neutron detector availability assessment system to obtain the high-voltage characteristic curve. By obtaining the high-voltage characteristic curve from the neutron detector availability assessment system, it is possible to further analyze the plateau change trend of the neutron detector and the voltage margin of the high-voltage characteristic curve to determine the availability of the neutron detector.

[0045] Next, step S20 is executed to obtain the plateau slope of the neutron detector in the current fuel cycle according to the high-voltage characteristic curve and the operating voltage of the neutron detector.

[0046] After obtaining the high-pressure characteristic curve, the neutron detector availability assessment system can analyze the plateau change trend of the high-pressure characteristic curve to obtain the plateau slope change of the plateau in the current fuel cycle. When the plateau slope does not meet the requirements of the relevant standards, the unavailability of the neutron detector in the current fuel cycle is determined, and the neutron detector needs to be replaced to ensure that the neutron detector can operate in a stable plateau.

[0047] In step S20, obtaining the plateau slope of the neutron detector in the current fuel cycle according to the high-voltage characteristic curve and the operating voltage of the neutron detector may further include:

[0048] According to the high-voltage characteristic curve, the plateau area of ​​the neutron detector is obtained;

[0049] The plateau slope of the neutron detector in the current fuel cycle is obtained based on the plateau area and the operating voltage.

[0050] In the process of calculating the plateau slope using the high-voltage characteristic curve in the neutron detector availability assessment system, the plateau area of ​​the neutron detector is first determined based on the high-voltage characteristic curve. The plateau area can be expressed as the corresponding interval of the high-voltage characteristic curve where the output current of the neutron detector remains basically constant as the applied voltage increases. Figure 2 The high-voltage characteristic curve of a neutron detector at a stable flux level is shown. It can be seen that when the applied voltage is between 0 and 140 V, the output current increases as the applied voltage continues to increase. After reaching 140 V, the output current remains essentially constant as the applied voltage continues to increase. The voltage-output current curve segment corresponding to this constant output current is the plateau region of the high-voltage characteristic curve. After determining the plateau region, the plateau slope of the plateau region at different operating voltages is calculated to further determine the availability of the neutron detector during the current fuel cycle. This allows for the timely replacement of neutron detectors after the current fuel cycle if they become unavailable due to plateau slope, maximizing neutron detector utilization while improving the economic benefits of nuclear power unit operation.

[0051] Wherein, obtaining the plateau slope of the neutron detector in the current fuel cycle according to the plateau area and the operating voltage may further include:

[0052] Obtaining a first output current value and a second output current value according to an operating voltage and a preset value, wherein the operating voltage corresponds to an applied voltage for normal operation of the neutron detector;

[0053] The plateau slope of the neutron detector in the current fuel cycle is obtained according to the current output current value, the first output current value, and the second output current value corresponding to the operating voltage.

[0054] During the calculation of the plateau slope of the neutron detector in the current fuel cycle by the neutron detector availability assessment system, the plateau section of the plateau slope calculation can be calculated based on the working voltage and the preset value in the plateau area. That is, the first working voltage before the working voltage can be determined by the difference between the working voltage and the preset value, and the second working voltage after the working voltage can be determined by the sum of the working voltage and the preset value. Then, the first working voltage is used to determine the corresponding first output current value, and the second working voltage is used to determine the corresponding second output current value. Further, the current output current value corresponding to the working voltage is used to calculate the plateau slope of the neutron detector in the current fuel cycle, so that the calculated plateau slope can be used to determine whether the plateau slope under the corresponding working voltage meets the requirements of the relevant standards. When the plateau slopes corresponding to the working voltages in the plateau area do not meet the requirements of the relevant standards, the corresponding neutron detectors should be replaced in a timely manner after the end of the current fuel cycle. When the plateau slopes corresponding to the various operating voltages in the plateau area meet the requirements of the relevant standards, it is determined that the plateau change trend of the high-voltage characteristic curve of the neutron detector in the current fuel cycle meets the requirements; in addition, it is also necessary to analyze whether the voltage margin of the high-voltage characteristic curve meets the requirements to comprehensively determine whether the neutron detector is usable, and to replace the neutron detector in a timely manner if it is unusable.

[0055] Furthermore, the calculation formula of the slope is: S = (I U+X -I U-X ) / I×100%; where X is the preset value, I U+X is the first output current value corresponding to the voltage U+X, I U-X is the second output current value corresponding to the voltage UX, the voltage UX is the first operating voltage, the voltage U+X is the second operating voltage, and I is the current output current value corresponding to the voltage U.

[0056] Assuming that the minimum value of the applied voltage in the current plateau is 140V, when the working voltage U of the neutron detector is 600V, if the preset value X is 100V, the first working voltage UX is 500V and the second working voltage UX is 700V. According to the first output current value I corresponding to the first working voltage 500V U+X , the second output current value corresponding to the second working voltage 700V, and the current output current value I corresponding to the current working voltage 600V can be calculated by the formula: S=(I U+X -I U-X) / I × 100% to calculate the plateau slope S of the neutron detector during the current fuel cycle. Generally, to ensure the neutron detector operates in a stable plateau region, the plateau slope S must be below a certain standard value. This standard value can be adjusted based on the type of neutron detector. For example, a uranium-coated fission chamber can have a standard value of 4%, while a boron-coated ionization chamber can have a standard value of 1.5%. If a plateau slope S in the high-pressure characteristic curve exceeds the standard value, the current neutron detector is unusable and needs to be replaced after the current fuel cycle.

[0057] Next, step S30 is performed to obtain 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 required to be measured by the neutron detector, the operating voltage of the neutron detector, and the upper limit of the low-voltage region voltage of the neutron detector. The voltage margin of the high-voltage characteristic curve may include a plateau voltage margin and a low applied voltage margin.

[0058] See also Figure 3 , Figure 3 In one embodiment, it can be seen that when the applied voltage is within the range of 0 to 140 V, the output current increases as the applied voltage continues to increase. This high-voltage characteristic curve section can be represented as the low applied voltage region. After the applied voltage reaches 140 V, the output current remains essentially constant as the applied voltage continues to increase. This high-voltage characteristic curve section 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's important to consider not only the impact of the plateau's changing trends on the detector's availability, but also the impact of the voltage margin of the high-voltage characteristic curve on the detector's availability. When considering the impact of the voltage margin of the high-voltage characteristic curve on the detector's availability, the low applied voltage margin affects the detector's availability in the low-applied voltage region of the high-voltage characteristic curve, while the plateau voltage margin also affects the detector's availability in the plateau region of the high-voltage characteristic curve. Therefore, the availability of a neutron detector can be further determined by analyzing the changes in the plateau voltage margin and the low applied voltage margin.

[0060] See also Figure 4 and Figure 5 , Figure 4 and Figure 5 In one embodiment, Figure 4The high-voltage characteristic curves of the neutron detector at a power level of 30% FP (FP refers to the full reactor power) and a power level of 100% FP are shown. It can be seen that the saturation current inflection point voltage at the 30% FP power level appears before 100V, and the saturation current inflection point voltage at the 100% FP power level appears after 100V, that is, the saturation current inflection point voltage at the 30% FP power level is smaller than the saturation current inflection point voltage at the 100% FP power level. This shows that in the high-voltage characteristic curves of the same neutron detector at different power levels in the same fuel cycle, the voltage corresponding to the saturation current inflection point is different; that is, as the power level increases, the inflection point voltage becomes larger. In addition, Figure 5 The high-voltage characteristic curves of the neutron detector at the same power level at different times are shown. It can be seen that the saturation current of the high-voltage characteristic curve corresponding to the same power level is basically the same. The saturation current inflection point of the neutron detector high-voltage characteristic curve in the first fuel cycle is the smallest, and the high-voltage characteristic curve has the largest plateau area. The saturation current inflection point of the neutron detector high-voltage characteristic curve in the N+1 fuel cycle is the second largest, and the high-voltage characteristic curve has the second largest plateau area. The saturation current inflection point of the neutron detector high-voltage characteristic curve in the 2N+1 fuel cycle is the largest, and the high-voltage characteristic curve has the smallest plateau area. This shows that as the unit's fuel cycles increase, the neutron detector gradually ages, and the plateau area of ​​the neutron detector high-voltage characteristic curve gradually decreases. The plateau voltage margin can then be used to evaluate the aging degree of the neutron detector in different fuel cycles.

[0061] In step S30, when calculating the plateau voltage margin, obtaining the voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage, and the upper limit of the low-voltage region voltage of the neutron detector may further include:

[0062] Obtaining a first conservative voltage according to a saturation current of a high-voltage characteristic curve and a first conservative parameter value;

[0063] The power level upper limit 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. The plateau voltage margin of the neutron detector for the current fuel cycle is then calculated based on this first conservative voltage, the current neutron detector operating voltage, the current reactor power level, and the upper limit of the power level required for the neutron detector measurement. This allows the plateau voltage margin to be used to determine 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 unavailable. If the plateau voltage margin meets the corresponding requirements, it is necessary to further determine the relevant conditions of the plateau slope and the low external voltage margin to comprehensively determine the availability of the neutron detector. This allows a comprehensive assessment of the current neutron detector availability without changing the equipment in the off-core nuclear instrumentation system.

[0065] The step of obtaining the first conservative voltage according to the saturation current of the high-voltage characteristic curve and the first conservative parameter value includes:

[0066] Obtaining a first conservative current according to the saturation current and the first conservative parameter value;

[0067] A first conservative voltage is obtained according to the first conservative current.

[0068] In the process of 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, the corresponding first conservative voltage can be determined by using the correspondence between the first conservative current and the high-voltage characteristic curve.

[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, the first conservative current I a =I sat ×a, the first conservative voltage is the external voltage value corresponding to the first conservative current in the high-voltage characteristic curve, wherein the larger the value of a is, the higher the first conservative voltage U a For example, a can take the empirical value of 0.9, or other values.

[0070] Furthermore, the availability of the corresponding neutron detector can be evaluated by the plateau voltage margin. The calculation formula of the plateau voltage margin is:

[0071]

[0072] Among them, V1 is the voltage margin in the plateau area, U is the operating voltage, and U a is the first conservative voltage, P is the current power level, P UThe upper limit of the power level that the neutron detector needs to measure. The reactor power level can be measured through KME thermal balance tests or other power measurement methods in nuclear power plants. Of course, it can also be further calculated by measuring the neutron flux leaking from the reactor using neutron detectors.

[0073] When using the calculation formula of the plateau voltage margin, it is assumed that the working voltage of the neutron detector in the current working state is U and the upper limit of the required measurement power is P U (If the neutron detector can measure the reactor power level range from 0 to 200% FP, then P U That is 200% FP; of course, the range of reactor power level measured by the neutron detector can also be other ranges, P U It can also be other values), the reactor power level where the high voltage characteristic curve is located is the current power level P, according to the saturation current I sat , the first conservative parameter value a, can predetermine the corresponding first conservative voltage U a Then, use the calculation formula of the plateau voltage margin: The plateau voltage margin of the neutron detector in the current fuel cycle is calculated, so that the aging degree of the corresponding neutron detector can be evaluated according to the plateau voltage margin, and then its availability can be determined.

[0074] The aging degree of the neutron detector is not only affected by the reduction of the voltage margin in the plateau area, but also manifested in the rightward shift of the characteristic curve in the low applied voltage area. Figure 6 Shown Figure 5 The low-voltage characteristic curves corresponding to the 0-100V range of the high-voltage characteristic curves of the neutron detector at the same power level at different times are shown. It can be seen that the low-voltage characteristic curves for the 1st fuel cycle, the N+1th fuel cycle, and the 2N+1th fuel cycle shift rightward. The low applied voltage margin corresponding to the low-voltage characteristic curves can be used to evaluate the aging of the neutron detector.

[0075] In step S30, when calculating the low applied voltage margin, the voltage margin of the high voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage, and the upper limit of the low voltage region of the neutron detector, including:

[0076] Obtaining a second conservative voltage according to the saturation current of the high-voltage characteristic curve and the second conservative parameter value;

[0077] According to the second conservative voltage and the upper voltage limit of the low-voltage zone, a low external voltage margin of the neutron detector in the current fuel cycle is obtained.

[0078] When calculating the low applied voltage margin using the neutron detector availability assessment system, a second conservative voltage can be calculated based on the saturation current of the high-voltage characteristic curve and a set second conservative parameter value. Then, based on the second conservative voltage and the current upper limit of the low-voltage region of the neutron detector, the low applied voltage margin of the neutron detector for the current fuel cycle is calculated, so that the availability of the neutron detector can be determined using the low applied voltage margin. When the low applied voltage margin does not meet the corresponding requirements, it can be directly determined that the neutron detector is unavailable. When the low applied voltage margin meets the corresponding requirements, it is necessary to further determine the relevant conditions of the plateau slope and the plateau voltage margin to comprehensively determine the availability of the neutron detector. In this way, the availability of the current neutron detector can be comprehensively evaluated without changing the equipment of the off-core nuclear instrument system.

[0079] The step of obtaining the second conservative voltage according to the saturation current of the high-voltage characteristic curve and the second conservative parameter value includes:

[0080] Obtaining a second conservative current according to the saturation current and the second conservative parameter value;

[0081] A second conservative voltage is obtained according to the second conservative current.

[0082] In the process of calculating the second conservative voltage, the second conservative current can be directly determined based on the saturation current of the high-voltage characteristic curve and the second conservative parameter value. Then, the corresponding second conservative voltage can be determined by using the corresponding relationship between the second conservative current and the high-voltage characteristic curve.

[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, the second conservative current I b =I sat ×b, the second conservative voltage is the external voltage value corresponding to the second conservative current in the high voltage characteristic curve, wherein the larger the value of b, the greater the second conservative voltage V b For example, b can take the empirical value of 0.2, or other values.

[0084] Furthermore, the availability of the corresponding neutron detector can be evaluated by the low applied voltage margin. The calculation formula of the low applied voltage margin is:

[0085] V2=V0-V b ;

[0086] Among them, V2 is the second available margin, V0 is the upper limit of the low voltage area selected according to the detector type, V b is the second conservative voltage.

[0087] When using the calculation formula of low applied voltage margin, it is assumed that the working voltage of the neutron detector in the current working state is U and the upper limit of the required measurement power is P U (If the neutron detector can measure the reactor power level range from 0 to 200% FP, then P U That is 200% FP; of course, the range of reactor power level measured by the neutron detector can also be other ranges, P U It can also be other values), the reactor power level where the high voltage characteristic curve is located is the current power level P, according to the saturation current I sat , the second conservative parameter value is b, and the corresponding second conservative voltage V b Then, use the formula for calculating the low applied voltage margin: V2 = V0 - V b , the low applied voltage margin of the neutron detector in the current fuel cycle is calculated, so that the aging degree of the corresponding neutron detector can be evaluated according to the low applied voltage margin, and then its availability can be determined.

[0088] Next, step S40 is executed to determine the availability of the neutron detector according to the plateau slope and the voltage margin of the high-voltage characteristic curve.

[0089] To ensure that the neutron detector operates in a stable plateau region, the plateau slope of the detector's high-voltage characteristic curve must be less than the plateau slope threshold specified in the relevant standards. This plateau slope threshold varies by neutron detector type. For example, the plateau slope threshold for a uranium-coated fission chamber can be 4%, while that for a boron-coated ionization chamber can be 1.5%. Other plateau slope thresholds can also be selected for uranium-coated fission chambers and boron-coated ionization chambers. The neutron detector availability assessment system calculates the plateau slope of the neutron detector's high-voltage characteristic curve during the current fuel cycle. If the plateau slope is less than the plateau slope threshold, the detector is operating in a stable plateau region. The detector's availability can be further determined by determining whether the voltage margin of the high-voltage characteristic curve meets relevant requirements. If the plateau slope is greater than or equal to the plateau slope threshold, the detector's plateau region is unstable and unusable, requiring replacement after the current fuel cycle.

[0090] The voltage margin of the high-voltage characteristic curve includes the plateau voltage margin and the low applied voltage margin.

[0091] When the neutron detector availability assessment system calculates the plateau voltage margin within the high-voltage characteristic curve, the smaller the plateau voltage margin, the more severe the detector neutron aging. If the plateau voltage margin approaches a set value (such as 0, but other values ​​are possible), it indicates that the aging level of the current fuel cycle is severe and there is no longer sufficient plateau voltage margin to support 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 within the high-voltage characteristic curve voltage margin, a smaller low applied voltage margin indicates more severe detector neutron aging. If the low applied voltage margin approaches a set value (e.g., 0, but other values ​​are possible), it indicates that the current fuel cycle has severely degraded the detector and that there is no longer sufficient low applied voltage margin to support stable neutron detector operation. 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 according to the plateau slope and the voltage margin of the high-voltage characteristic curve, the method further includes:

[0094] 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 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 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. This can predict the fuel cycle timing when the neutron detector is unavailable, avoiding the situation where the detector is still operational at the beginning of a fuel cycle but the detector function deteriorates before the end of the fuel cycle, resulting in unplanned shutdown of the nuclear power unit for detector replacement, affecting the economic efficiency of the nuclear power plant.

[0096] Furthermore, 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 the previous fuel cycle, including:

[0097] Predicting the voltage margin of the high-voltage characteristic curve of 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 the previous fuel cycle to obtain a predicted value of the voltage margin of the high-voltage characteristic curve of the next fuel cycle;

[0098] When the voltage margin prediction value of the high-voltage characteristic curve is less than the set value, the neutron detector enters the refueling overhaul and replacement period after the current fuel cycle ends.

[0099] After obtaining the voltage margins of the high-voltage characteristic curves of the neutron detectors for the current fuel cycle and the previous fuel cycle, the neutron detector availability assessment system can utilize multiple voltage margins of the high-voltage characteristic curves of the neutron detectors corresponding to the current fuel cycle and the previous fuel cycle, and, for example, through least squares method or other methods, derive the trend of the high-voltage characteristic curve voltage margins changing with the fuel cycle, thereby predicting the predicted value of the high-voltage characteristic curve voltage margin for the next fuel cycle. If the predicted value of the high-voltage characteristic curve voltage margin is less than a set value, it indicates that the neutron detector will be unavailable after the end of the current fuel cycle, and the end of the current fuel cycle will be used as the refueling overhaul and replacement period for the neutron detector.

[0100] Specifically, when predicting the refueling overhaul period for a neutron detector based on the plateau voltage margins of the neutron detector in the current fuel cycle and the previous fuel cycle, the multiple plateau voltage margins of the neutron detector corresponding to the current fuel cycle and the previous fuel cycle can be used to derive the trend of the plateau voltage margin as the fuel cycle changes, for example, using the least squares method or other methods, thereby predicting the predicted 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 will be the fuel cycle time when the neutron detector is unavailable, and the end of the current fuel cycle will be used as the refueling overhaul period for the neutron detector.

[0101] See also 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 using the fuel cycle as a unit, and the trend of the plateau voltage margin changing with the fuel cycle can be obtained based on the fuel cycle and the plateau voltage margin. Except for the first fuel cycle, each fuel cycle of a nuclear power plant is generally about 18 months, although other time periods are also possible. By using the trend of the plateau voltage margin changing with the fuel cycle, it is possible to predict the timing of a fuel cycle in which the neutron detector will be unavailable near the end of the fuel cycle by utilizing the trend of the plateau voltage margin corresponding to the current fuel cycle and the previous fuel cycle. Based on this, the neutron detector can be replaced during a refueling overhaul before the predicted fuel cycle arrives, thereby providing operation and maintenance personnel with a forward-looking prediction of the timing of neutron detector replacement. This improves detector utilization while avoiding affecting the normal operation of the nuclear power unit and improving the operational efficiency of the nuclear power unit.

[0102] Similarly, when predicting the refueling overhaul replacement period of a neutron detector based on the low applied voltage margin of the neutron detector in the current fuel cycle and the previous fuel cycle, the multiple low applied voltage margins of the neutron detector corresponding to the current fuel cycle and the previous fuel cycle can be used to obtain the trend of the low applied voltage margin changing with the fuel cycle, such as through the least squares method or other methods, so as to predict the low applied voltage margin prediction value for the next fuel cycle. If the low applied voltage margin prediction value is less than the set value, it means that the fuel cycle after the end of the current fuel cycle is unavailable, and the refueling overhaul replacement period of the neutron detector is set after the end of the current fuel cycle.

[0103] See also Figure 8 , Figure 8 In one embodiment, a low applied voltage margin for the neutron detector high-voltage characteristic curve can be obtained for each fuel cycle, using the fuel cycle as a unit. Furthermore, based on the fuel cycle and the low applied voltage margin, a trend of the low applied voltage margin changing with the fuel cycle can be obtained. Except for the first fuel cycle, each fuel cycle of a nuclear power plant is typically approximately 18 months, though other time periods are also possible. By using the trend of the low applied voltage margin changing with the fuel cycle, it is possible to predict the timing of a fuel cycle in which the neutron detector will be unavailable near the end of the fuel cycle by utilizing the trend of the low applied voltage margin corresponding to the current fuel cycle and the previous fuel cycle. Based on this, the neutron detector can be replaced during a refueling overhaul before the predicted fuel cycle arrives, thereby providing operators with a proactive prediction of the timing of neutron detector replacement. This improves detector utilization while avoiding disruptions to the normal operation of the nuclear power unit, thereby enhancing the operational efficiency of the nuclear power unit.

[0104] Please refer to 9. The present invention also provides a neutron detector availability assessment system 11, including: an acquisition unit 111, used to obtain the high-voltage characteristic curve of the neutron detector in the current fuel cycle; a plateau calculation unit 112, used to obtain the plateau of the neutron detector in the current fuel cycle based on the high-voltage characteristic curve; a margin calculation unit 113, used to obtain the voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage of the neutron detector and the upper limit of the low-voltage zone voltage of the neutron detector; and a determination unit 114, used to determine the availability of the neutron detector based on the plateau and the voltage margin of the high-voltage characteristic curve.

[0105] It should be noted that the neutron detector availability assessment system 11 provided in the above embodiment and the neutron detector availability assessment method provided in the above embodiment are based on the same concept. The specific manner in which each module and unit performs operations has been described in detail in the method embodiment and will not be repeated here. In actual applications, the neutron detector availability assessment system 11 provided in the above embodiment can, as needed, allocate the above functions to different functional modules, that is, divide the internal structure of the device into different functional modules to complete all or part of the functions described above, and this is not limited here.

[0106] See also 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, including a flash memory, a mobile hard disk, a multimedia card, a card-type memory (e.g., SD or DX memory), a magnetic memory, a magnetic disk, an optical disk, etc. In some embodiments, the memory 12 may be an internal storage unit of the electronic device 1, such as a mobile hard disk of the electronic device 1. In other embodiments, the memory 12 may also be an external storage device of the electronic device 1, such as a plug-in mobile hard disk, a smart memory card (SMC), a secure digital (SD) card, a flash card, etc. equipped on the electronic device 1. Furthermore, the memory 12 may include both an internal storage unit of the electronic device 1 and an external storage device. The memory 12 may be used not only to store application software and various types of data installed in the electronic device 1, such as the code for the neutron detector availability assessment, but also to temporarily store data that has been output or is about to be output.

[0108] In some embodiments, the processor 13 may be composed of an integrated circuit, such as a single packaged integrated circuit, or a plurality of packaged integrated circuits with the same or different functions, including one or more central processing units (CPUs), microprocessors, digital processing chips, graphics processors, and a combination of various control chips. The processor 13 is the control core (Control Unit) of the electronic device 1, connecting the various components of the entire electronic device 1 using various interfaces and circuits. It executes or runs programs or modules stored in the memory 12 (such as a neutron detector availability assessment program) and calls data stored in the memory 12 to perform various functions of the electronic device 1 and process data.

[0109] The processor 13 executes the operating system and various installed application programs of the electronic device 1. The processor 13 executes the application programs to implement the steps in the above-mentioned neutron detector availability assessment method.

[0110] Exemplarily, 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 implement the present 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 above-mentioned integrated unit implemented in the form of a software functional module can be stored in a computer-readable storage medium, which can be non-volatile or volatile. The above-mentioned software functional module is stored in a storage medium and includes a number of instructions for causing a computer device (which can be a personal computer, computer device, or network device, etc.) or a processor to perform part of the functions of the neutron detector availability assessment method described in various embodiments of the present application.

[0112] In summary, the present invention discloses a neutron detector availability assessment method, system, device, and medium. By utilizing the high-voltage characteristic curve of the neutron detector during the current fuel cycle, the system determines the plateau slope and voltage margin of the high-voltage characteristic curve during the current fuel cycle. This allows for a comprehensive assessment of the current neutron detector's availability based on the plateau slope and voltage margin of the high-voltage characteristic curve, without changing the equipment in the off-core nuclear instrumentation system. Furthermore, the system can predict the remaining useful life of the neutron detector based on the voltage margin of the high-voltage characteristic curve of the neutron detector during the current fuel cycle and the previous fuel cycle. This allows the system to initiate a refueling and overhaul replacement period for the neutron detector if the neutron detector is predicted to be unavailable during the fuel cycle before the predicted fuel cycle in which the neutron detector is unavailable. This provides maintenance personnel with a proactive assessment of the timing of neutron detector replacement, improves detector utilization, avoids impacting the normal operation of the nuclear power unit, and improves the operational efficiency of the nuclear power unit. Therefore, the present invention effectively overcomes the various shortcomings of the prior art and possesses high industrial value.

[0113] The above embodiments are merely illustrative of the principles and effects of the present invention and are not intended to limit the present invention. Anyone skilled in the art may 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 one of ordinary skill in the art without departing from the spirit and technical principles disclosed herein are intended to be covered by the claims of the present invention.

Claims

1. A method for evaluating the availability of a neutron detector, characterized in that: include: Obtaining the high-voltage characteristic curve of the neutron detector during the current fuel cycle; obtaining a plateau slope of the neutron detector in a current fuel cycle according to the high-voltage characteristic curve and the operating voltage of the neutron detector; Obtaining a voltage margin of the high-voltage characteristic curve of the neutron detector in 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 required to be measured by the neutron detector, the operating voltage, and the upper limit of the voltage in the low-voltage region of the neutron detector; The availability of the neutron detector is determined according to the plateau slope and the voltage margin of the high-voltage characteristic curve.

2. The neutron detector availability assessment method according to claim 1, characterized in that: Obtaining a plateau slope of the neutron detector in a current fuel cycle according to the high-voltage characteristic curve and the operating voltage of the neutron detector, including: acquiring the plateau region of the neutron detector according to the high-voltage characteristic curve; The plateau slope of the neutron detector in the current fuel cycle is obtained according to the plateau area and the operating voltage.

3. The neutron detector availability assessment method according to claim 2, characterized in that: Obtaining a plateau slope of the neutron detector in a current fuel cycle according to the plateau area and the operating voltage, comprising: Obtaining a first output current value and a second output current value according to the operating voltage and a preset value; The plateau slope of the neutron detector in the current fuel cycle is obtained according to the current output current value corresponding to the operating voltage, the first output current value, and the second output current value.

4. The neutron detector availability assessment method according to claim 3, characterized in that: The calculation formula of the flat slope is: S=(I U+X -I U-X ) / I×100%; Among them, X is the preset value, I U+X is the first output current value corresponding to the voltage U+X, I U-X is the second output current value corresponding to the voltage UX, and I is the current output current value corresponding to the voltage U.

5. The neutron detector availability assessment method according to claim 1, characterized in that: The voltage margin of the high-voltage characteristic curve includes a plateau voltage margin; Obtaining a voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle according to the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level required to be measured by the neutron detector, the operating voltage, and the upper limit of the voltage in the low-voltage region of the neutron detector, including: Obtaining the first conservative voltage according to the saturation current of the high-voltage characteristic curve and a first conservative parameter value; The plateau voltage margin of the neutron detector in the current fuel cycle is obtained according to the first conservative voltage, the operating voltage, the current power level and the upper limit of the power level measured by the neutron detector requirement.

6. The neutron detector availability assessment method according to claim 5, characterized in that: Obtaining the first conservative voltage according to the saturation current of the high-voltage characteristic curve and a first conservative parameter value includes: Obtaining a first conservative current according to the saturation current and a first conservative parameter value; The first conservative voltage is obtained according to the first conservative current.

7. The neutron detector availability assessment method according to claim 5, characterized in that: The calculation formula of the plateau voltage margin is: Among them, V1 is the voltage margin in the plateau area, U is the operating voltage, and U a is the first conservative voltage, P is the current power level, P U Upper limit of power levels measured for neutron detector requirements.

8. The neutron detector availability assessment method according to claim 1, characterized in that: The voltage margin of the high voltage characteristic curve includes a low applied voltage margin; Obtaining a voltage margin of the high-voltage characteristic curve of the neutron detector in the current fuel cycle according to the high-voltage characteristic curve, the current power level of the reactor, the upper limit of the power level required to be measured by the neutron detector, the operating voltage, and the upper limit of the voltage in the low-voltage region of the neutron detector, including: Obtaining the second conservative voltage according to the saturation current of the high-voltage characteristic curve and the second conservative parameter value; The low applied voltage margin of the neutron detector in the current fuel cycle is obtained according to the second conservative voltage and the upper voltage limit of the low voltage zone.

9. The neutron detector availability assessment method according to claim 8, characterized in that: Obtaining the second conservative voltage according to the saturation current of the high-voltage characteristic curve and the second conservative parameter value includes: Obtaining a second conservative current according to the saturation current and the second conservative parameter value; The second conservative voltage is obtained according to the second conservative current.

10. The neutron detector availability assessment method according to claim 8, characterized in that: The calculation formula of the low applied voltage margin is: V2=V0-V b ; Among them, V2 is the low external voltage margin, V0 is the upper limit of the low voltage area selected according to the detector type, V b is the second conservative voltage.

11. 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 the previous fuel cycle.

12. The neutron detector availability assessment method according to claim 11, characterized in that: Predicting a refueling overhaul replacement period of the neutron detector based on a voltage margin of the high-voltage characteristic curve of the neutron detector in a current fuel cycle and a previous fuel cycle, including: 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 the previous fuel cycle to obtain a predicted value of the voltage margin of the high-voltage characteristic curve for the next fuel cycle; When the voltage margin prediction value of the high-voltage characteristic curve is less than the set value, the neutron detector enters a refueling overhaul and replacement period after the current fuel cycle ends.

13. A neutron detector availability assessment system, characterized in that: include: An acquisition unit, used for acquiring a high-voltage characteristic curve of the neutron detector in the current fuel cycle; a plateau slope calculation unit, configured to obtain the plateau slope of the neutron detector in the current fuel cycle according to the high-pressure characteristic curve; a margin calculation unit, configured to obtain a voltage margin of the high-voltage characteristic curve of the neutron detector in a current fuel cycle based on the high-voltage characteristic curve, the current power level of the reactor, an upper limit of the power level required to be measured by the neutron detector, an operating voltage of the neutron detector, and an upper limit of the voltage in the low-voltage region of the neutron detector; as well as A determining unit is configured to determine the availability of the neutron detector according to the plateau slope and the voltage margin of the high-voltage characteristic curve.

14. An electronic device, characterized in that: The electronic device comprises: one or more processors; A storage device for storing one or more programs, which, when executed by the one or more processors, enables the electronic device to implement the neutron detector availability assessment method according to any one of claims 1 to 12.

15. A computer-readable storage medium, characterized in that A computer program is stored thereon, and when the computer program is executed by a processor of a computer, the computer is caused to execute the neutron detector availability assessment method according to any one of claims 1 to 12.

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