CN115685311A - Current calibration method and system for reactor core nuclear measurement self-powered detector - Google Patents
Current calibration method and system for reactor core nuclear measurement self-powered detector Download PDFInfo
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Abstract
The invention discloses a current calibration method and a system for a reactor core nuclear self-power-supply detector, wherein the method comprises the following steps: s1, acquiring a first data set and a second data set detected by a detector to be calibrated; wherein the first data set includes a first current detected by the detector at a first time during a reactor shutdown operation; the second data group comprises a second current detected by the detector at a second moment after the reactor shutdown operation; s2, determining gamma current generated by the detector to be calibrated due to gamma effect according to the first data group and the second data group; and S3, subtracting each current from each current measured by the detector to be calibrated, subtracting the gamma current generated by the detector to be calibrated due to the gamma effect, and determining the gamma share of the detector to be calibrated. By using the method, the gamma share current of the detector can be accurately eliminated so as to calibrate the reading of the detector, and meanwhile, the method can be used for measuring and calculating the response time of the detector.
Description
Technical Field
The invention relates to the field of nuclear power, in particular to a current calibration method and system for a reactor core nuclear self-power-supply detector.
Background
The self-powered detector is a detector capable of detecting neutrons or gamma rays without an external power supply. The reactor core nuclear measurement system is widely applied to the reactor core nuclear measurement system of the third-generation advanced pressurized water reactor due to the characteristics of simple structure, small size, high precision, long service life, good stability, no need of an external power supply and the like, and is used for carrying out on-line measurement on the thermal neutron fluence rate distribution of the reactor core of the reactor, thereby improving the safety of the operation of the reactor. Since both neutrons and gamma rays are typically incident during reactor operation, the detectors also react with gamma rays in the core, producing a gamma current. The current detected by the current technology includes not only delayed current generated by neutrons, but also gamma current, and the core-based nuclear measurement is mainly used for measuring the distribution of neutron fluence in the core, so that the gamma component in the output current of the self-powered core detector needs to be corrected.
Disclosure of Invention
The invention aims to provide a method and a system for calibrating current of a self-powered detector for nuclear reactor core measurement in order to correct a gamma component in output current of the detector.
The invention solves the technical problems through the following technical scheme:
in a first aspect of the present invention, the present invention provides a method for calibrating a current of a self-powered probe for nuclear reactor core test, the method comprising:
s1, acquiring a first data set and a second data set detected by a detector to be calibrated;
wherein the first data set includes a first current detected by the detector at a first time during a reactor trip operation; the second data set comprises a second current detected by the detector at a second time after the reactor shutdown operation;
s2, determining a gamma current generated by the detector to be calibrated due to a gamma effect according to the first data group and the second data group;
and S3, subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated, and determining the gamma share of the detector to be calibrated.
Preferably, the step of determining the gamma current generated by the detector to be calibrated due to the gamma effect from the first data set and the second data set specifically includes the following steps:
by passing
Determining the gamma current generated by the detector to be calibrated due to the gamma effect;
wherein t represents the time after the reactor shutdown operation; i is t Representing the current measured by the detector at time t; t is 1/2 Represents the half-life of the emission material of the detector; i is 0 The slow-release current generated by the reaction of the detector and the neutrons at the time of the reactor shutdown operation is represented; k represents a gamma current generated by the detector due to a gamma effect when the reactor is in shutdown operation;
and determining the response time of the detector to be calibrated according to the solved detection formula.
Preferably, the method for calibrating the current of the nuclear self-powered probe for core nuclear measurement further comprises the following steps:
acquiring gamma current generated by a standard detector due to a gamma effect and a gamma share of the standard detector according to the steps S1-S3;
acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector,
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
Preferably, the method for calibrating the current of the nuclear self-powered probe for core nuclear measurement further comprises the following steps:
and obtaining an attenuation current curve of the detector to be calibrated, and determining that the current calibration of the detector to be calibrated is finished when the current difference value of the attenuation current curve at a certain moment and the time corresponding to the detection formula is in accordance with a preset current difference value and the fitting degree of the attenuation current curve and the curve corresponding to the detection formula is in accordance with a preset fitting degree.
Preferably, if the current calibration of the detector to be calibrated is not completed, the current calibration method for the nuclear-core self-powered detector comprises the following steps:
acquiring a third data set comprising a third current detected by the detector at a third time after the reactor shutdown operation;
wherein the third time is greater than the second time;
and determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the third data group, and determining a new gamma share of the detector to be calibrated.
As a second aspect of the present invention, the present invention provides a system for calibrating a current of a nuclear self-powered core nuclear detector, the system comprising: the device comprises a data acquisition module, a gamma current determination module and a data calibration module;
the data acquisition module is used for acquiring a first data set and a second data set detected by the detector to be calibrated;
wherein the first data set includes a first current detected by the detector at a first time during a reactor trip operation; the second data set comprises a second current detected by the detector at a second time after the reactor shutdown operation;
the gamma current determining module is used for determining the gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the second data group;
the data calibration module is used for subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated and determining the gamma share of the detector to be calibrated.
Preferably, the gamma current determination module is specifically configured to pass
Determining the gamma current generated by the detector to be calibrated due to the gamma effect;
wherein t represents a time after a reactor shutdown operation; I.C. A t Representing the current measured by the detector at time t; t is 1/2 Half-life of the emitting material of the probe; i is 0 Representing slow-generating current generated by the reaction of the detector and neutrons at the shutdown operation moment; k represents a gamma current generated by the detector due to a gamma effect when the reactor is in shutdown operation;
and determining the response time of the detector to be calibrated according to the solved detection formula.
Preferably, the data acquisition module, the gamma current determination module and the data calibration module are called to acquire the gamma current generated by the standard detector due to the gamma effect and the gamma share of the standard detector;
the reactor core nuclear detection self-powered detector current calibration system further comprises a thermal neutron sensitivity module;
the thermal neutron sensitivity module is used for acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector;
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
Preferably, the reactor core nuclear power self-powered probe current calibration system further comprises a calibration judgment;
and the calibration judgment is used for acquiring an attenuation current curve of the detector to be calibrated, and when the current of the attenuation current curve at a certain moment and the current difference value of the time corresponding to the detection formula accord with a preset current difference value, and the fitting degree of the attenuation current curve and the curve corresponding to the detection formula accords with a preset fitting degree, the current calibration of the detector to be calibrated is determined to be completed.
Preferably, the data acquiring module is further configured to acquire a third data set, where the third data set includes a third current detected by the detector at a third time after the reactor shutdown operation;
wherein the third time is greater than the second time;
the gamma current determining module is further used for determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the third data group,
the data calibration module is further used for determining a new gamma share of the detector to be calibrated.
The positive progress effects of the invention are as follows: the current of the detector caused by the gamma effect can be accurately eliminated so as to calibrate the reading of the detector.
Drawings
Fig. 1 is a schematic flow chart of a current calibration method for a self-powered nuclear reactor core detector in embodiment 1 of the present invention.
Fig. 2 is a first comparative diagram of a curve of a detection formula and a decay current curve of a detector in embodiment 1 of the present invention.
Fig. 3 is a partially enlarged schematic view of fig. 2.
Fig. 4 is a second comparative diagram of a curve of the detection formula and a curve of the attenuation current of the detector in embodiment 1 of the present invention.
Fig. 5 is a schematic structural diagram of a current calibration system of a self-powered core nuclear detection detector in embodiment 2 of the present invention.
Detailed Description
The invention is further illustrated by the following examples, which are not intended to limit the scope of the invention.
Example 1
Referring to fig. 1, the present embodiment provides a method for calibrating a current of a self-powered core nuclear detector, the method includes:
s1, acquiring a first data set and a second data set detected by a detector to be calibrated;
wherein the first data set includes a first current detected by the detector at a first time during a reactor trip operation; the second data set comprises a second current detected by the detector at a second time after the reactor shutdown operation;
s2, determining a gamma current generated by the detector to be calibrated due to a gamma effect according to the first data group and the second data group;
and S3, subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated, and determining the gamma share of the detector to be calibrated.
In this embodiment, both neutrons and gamma rays are typically incident during reactor operation. The reactor gamma rays comprise instantaneous gamma rays generated by neutron capture, instantaneous gamma rays generated in the fission process and fission fragment delayed gamma rays. When the reactor is fast stopped, the neutron fluence rate and the prompt gamma-rays drop rapidly and approach zero, while the slow gamma-rays will continue. As gamma rays pass through the emitter and collector, the compton effect and the photoelectric effect occur, creating a transient current (referred to as "gamma current" above).
In a specific example of the present embodiment, the detector is a vanadium self-powered detector, whose basic principle is an emitter nucleus
Nuclear reaction with neutron to generate instantaneous gamma photon and generate
Instability proceeds with a half-life of 3.75min - Decay to produce
Excited state, beta - Electrons generated by decay pass through the insulator and finally reach the collector, and are processed by an electronic loop, so that a current signal in direct proportion to the neutron fluence rate can be finally obtained. During the nuclear reaction of the vanadium detector and the neutron, the generation of gamma rays is also accompanied, and the gamma rays pass through the emitter and the collector to generate a compton effect and a photoelectric effect, so that a transient current (namely, the gamma current generated by the quasi-detector due to the gamma effect) is generated.
With the present embodiment, the detector to be calibrated can be calibrated by subtracting the gamma current from each current measured by the detector to be calibrated. It should be noted that, when the detector is a vanadium self-powered detector, the gamma effect is negative. That is, the calculated gamma current is a negative value (in this case, the gamma current is about-5 to-8% of the total current). That is, it is necessary to reduce each measured current of the detector to be calibrated by a negative value.
Specifically, the step of determining the gamma current generated by the detector to be calibrated due to the gamma effect according to the first data set and the second data set may specifically include the following steps:
by passing
Determines the gamma effect of the detector to be calibratedA gamma current;
wherein t represents a time after a reactor shutdown operation; I.C. A t Representing the current measured by the detector at time t; t is 1/2 Represents the half-life of the emission material of the detector; I.C. A 0 The slow-release current generated by the reaction of the detector and the neutrons at the time of the reactor shutdown operation is represented; k represents a gamma current generated by the detector due to a gamma effect when the reactor is in shutdown operation;
and determining the response time of the detector to be calibrated according to the solved detection formula.
In the above embodiment, the process of determining the gamma current of the detector to be calibrated according to the detection formula is as follows:
the detection formula can be understood as
Wherein, due to T 1/2 Indicating the half-life of the emission material of the detector, which is known. The first data set and the second data set are substituted into a detection formula. For example, the first data set is: time 0 (i.e., the first time) and 148.8nA; the second data set is: 500 seconds (i.e., the second time), and 24.5nA. According to the first data group and the second data group, obtaining slow-release current generated by neutrons when the reactor stops operating (namely I in the detection formula) 0 ) And the gamma current generated by the detector to be calibrated due to the gamma effect when the reactor is in shutdown operation (namely, K in the detection formula, and the gamma current caused by the detector is replaced by K for convenience of description).
In the above embodiment, the response time of the detector (the current is reduced to 10 percent, and the time at this time is regarded as the response time of the detector) is determined according to the detection formula to re-determine the performance parameters of the detector.
Specifically, the method for calibrating the current of the self-powered detector for nuclear reactor core measurement can further comprise the following steps:
acquiring gamma current generated by a standard detector due to gamma effect and a gamma share of the standard detector according to the steps S1-S3;
acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector,
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
For example, a detector to be detected is selected, and the relative sensitivity of the detector to be detected is calculated to be 0.9984 by comparing the output current of the detector with the average current of a standard detector. And "K" of the detector to be tested is-8.27 nA, the first current is 145.54nA, and the ratio of the gamma current induced by the detector to be calibrated to the total current (i.e. the gamma fraction described above) is: -8.27/145.54= -5.68%. Similarly, it can be calculated that the "K" of the standard probe is-7.58 nA, the first current is 155.09nA, and the ratio of the instantaneous current induced by the standard calibration probe to the total current is: -4.89%. Then the new relative thermal neutron sensitivity is 0.9984 × 1.0568/1.0489=1.0059.
In this embodiment, thermal neutron sensitivity is one of the key nuclear performance parameters of the detector. The thermal neutron sensitivity of the detector is corrected by the method mentioned in the above embodiment. In the correction process, errors caused by uneven distribution of the neutron field in the pore canal are considered, and the linear relation between the shutdown and the instantaneous gamma field of the calibration power step can be properly corrected by referring to the relation between the gamma current of the compensation cable and the reactor power.
Specifically, the method for calibrating the current of the self-powered detector for nuclear reactor core measurement can further comprise the following steps:
and obtaining an attenuation current curve of the detector to be calibrated, and when the current of the attenuation current curve at a certain moment and the current difference value of the time corresponding to the detection formula accord with a preset current difference value, and the fitting degree of the attenuation current curve and the curve corresponding to the detection formula accords with a preset fitting degree, determining that the current calibration of the detector to be calibrated is completed.
In other embodiments, the detection formula is determined to correspond toCan be seen in fig. 2, as well as in fig. 3, as well as in the decay current curve of the detector. For example, the current at 1000S of the decaying current curve is-1.18 nanoamperes, and it can be known from the calculated detection formula that at 1000S, the corresponding current is-1.11 nanoamperes, the difference between the two is 0.07 nanoamperes (the preset current difference may be 0.10 nanoamperes), and the degree of fit of the two curves is R 2 =99.991% (e.g. 99% of the predetermined fit), it can be determined that the calibration of the detection curve is satisfactory, and the current calibration of the detector to be calibrated is completed.
In addition, in this embodiment, the following scheme may be adopted, that is, the same time point in the attenuation current curve and the detection formula is selected, and when the current difference between the attenuation current curve and the detection formula at the same time point is smaller than a preset difference, it may be determined that the calibration of the detection curve that is obtained meets the requirement, and the current calibration of the detector to be calibrated is completed. For example, it is preferable to select a screening current curve and a current difference value of the detection formula at 800 seconds, where the current difference value is less than 0.5 nanoamperes, and when the fitting degree of the attenuation current curve and the curve corresponding to the detection formula conforms to a preset fitting degree, it is determined that the current calibration of the detector to be calibrated is completed.
Specifically, if the current calibration of the detector to be calibrated is not completed, the current calibration method for the nuclear self-powered detector for core nuclear test may include the following steps:
acquiring a third data set, wherein the third data set comprises a third current detected by the detector at a third moment after the reactor shutdown operation;
wherein the third time is greater than the second time;
and determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data set and the third data set, and determining a new gamma share of the detector to be calibrated.
In this embodiment, if the second time of the second set of data is too short, the result obtained by "K" in the detection formula is inaccurate, and the calibration result of the detector to be calibrated is inaccurate.
In the above embodiment, please refer to fig. 4, fig. 4 is a result obtained by fitting the curve corresponding to the detection formula and the decay current curve. In one embodiment, when the fitting degree of the curve corresponding to the detection formula and the attenuation current curve satisfies the predetermined fitting degree, the calibration result of the detector to be calibrated may also be considered to satisfy the requirement.
In one embodiment, referring to the following table, a plurality of detectors to be calibrated (i.e., V1-V14 in the following table), a plurality of standard detectors (S1-S4 in the following table) may be included. The arrangement of the standard detector and the detector to be calibrated and the design and manufacture of the bracket are required to keep a circle center symmetrical structure. And calculating the 'K' corresponding to the detector to be calibrated a "(a represents the numbers of V1-V14 and S1-S4), the specific cases are shown in the following table:
| detector numbering | K(nA) | Detector numbering | K(nA) | Detector numbering | K(nA) |
| V1 | -8.27 | V7 | -8.17 | V13 | -8.38 |
| V2 | -8.35 | V8 | -8.11 | V14 | -8.29 |
| V3 | -8.20 | V9 | -8.44 | S1 | -7.58 |
| V4 | -8.28 | V10 | -8.43 | S2 | -7.72 |
| V5 | -8.25 | V11 | -8.36 | S3 | -7.51 |
| V6 | -8.19 | V12 | -8.42 | S4 | -7.34 |
And substituting the curve corresponding to the detection formula obtained by each detector into the normalization formula to obtain each normalization curve. The response time and half-life of the detector can be calculated through the steps.
In the above embodiment, taking the vanadium detector as an example, the detector to be tested is fixed on a corresponding rotatable bracket and placed in a suitable reactor test tunnel, and all the sensitive regions of the detector are ensured to be at the reactor core position, and the reactor is used to provide a stable neutron flux field for detecting the performance of the detector. The average value of 2 or more standard detectors can be used for carrying out sensitivity relative calibration on the detector to be calibrated, and the arrangement of the standard detectors and the detector to be calibrated and the design and manufacture of the bracket are required to keep a circle-center symmetrical structure. The error caused by the distribution of the neutron field in the calibrated pore channel can be eliminated by using a method of rotating the bracket at a fixed angle, and the positions of the standard detector and the detector to be calibrated in the rotating process are relatively fixed. Upon detection, in one example, the reactor power is ramped up in power steps and the support is rotated (e.g., by 45 °, 90 ° up to 360 °) at a target power (e.g., 19 MW) to eliminate neutron distribution induced bias. In one example, compensation cables may also be used for detecting gamma currents in the detector integration cables. Observing the output current of the compensation cable, it can be seen that the gamma of the core increases with increasing power. When the power of the reactor reaches 19MW, the response time compensation of the vanadium detector is considered, the neutron fluence rate reaches the peak value, but the current of the compensation cable reaches the peak value after about 1 hour. When the reactor is shut down for about half an hour, the vanadium detector current decays to about-3 nA, and the compensating cable current decreases to about-2 nA. The reactor gamma rays are illustrated to include transient gamma rays generated by neutron capture, transient gamma rays generated by the fission process and fission fragment delayed gamma rays.
It should be noted that the detector to be calibrated and the standard detector in the present embodiment 1 are both self-powered detectors.
Example 2
Referring to fig. 5, the present embodiment provides a system for calibrating current of a nuclear self-powered core nuclear detector, which includes: a data acquisition module 201, a gamma current determination module 202 and a data calibration module 203;
the data acquisition module 201 is configured to acquire a first data set and a second data set detected by a detector to be calibrated;
wherein the first data set includes a first current detected by the detector at a first time during a reactor trip operation; the second data set comprises a second current detected by the detector at a second time after the reactor shutdown operation;
the gamma current determining module 202 is configured to determine a gamma current generated by the detector to be calibrated due to a gamma effect according to the first data set and the second data set;
a data calibration module 203; the device is used for subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated and determining the gamma share of the detector to be calibrated.
In particular, the gamma current determination module 202 may be specifically configured to pass
Determining the gamma current generated by the detector to be calibrated due to the gamma effect;
wherein t represents the time after the reactor shutdown operation; i is t Representing the current measured by the detector at time t; t is 1/2 Half-life of the emitting material of the probe; I.C. A 0 Representing slow-generating current generated by the detector reacting with neutrons when the reactor is shut down; k represents a gamma current generated by the detector due to a gamma effect when the reactor is in shutdown operation;
and determining the response time of the detector to be calibrated according to the solved detection formula.
Specifically, the data acquisition module 201, the gamma current determination module 202 and the data calibration module 203 can be invoked to acquire the gamma current of the standard detector due to the gamma effect and the gamma share of the standard detector;
the reactor core nuclear detection self-powered detector current calibration system can also comprise a thermal neutron sensitivity module;
the thermal neutron sensitivity module can be used for acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector;
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
Specifically, the current calibration system for the reactor core nuclear self-powered detector further comprises calibration judgment;
and the calibration judgment is used for acquiring an attenuation current curve of the detector to be calibrated, and when the current of the attenuation current curve is not less than 1200 seconds and the current difference value of the time corresponding to the detection formula is consistent, the current calibration of the detector to be calibrated is determined to be completed.
Specifically, the data acquisition module 201 may be further configured to acquire a third data set, where the third data set includes a third current detected by the detector at a third time after the reactor shutdown operation;
wherein the third time is greater than the second time;
the gamma current determining module is further used for determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the third data group,
the data calibration module is further used for determining a new gamma share of the detector to be calibrated.
While specific embodiments of the invention have been described above, it will be understood by those skilled in the art that this is by way of example only, and that the scope of the invention is defined by the appended claims. Various changes or modifications to these embodiments may be made by those skilled in the art without departing from the principle and spirit of this invention, and these changes and modifications are within the scope of this invention.
Claims (10)
1. A method for calibrating current of a self-powered detector for nuclear reactor core measurement is characterized by comprising the following steps:
s1, acquiring a first data set and a second data set detected by a detector to be calibrated;
wherein the first data set includes a first current sensed by the detector at a first time during a reactor trip operation; the second data group comprises a second current detected by the detector at a second moment after the reactor shutdown operation;
s2, determining a gamma current generated by the detector to be calibrated due to a gamma effect according to the first data group and the second data group;
and S3, subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated, and determining the gamma share of the detector to be calibrated.
2. The method for calibrating current of a nuclear-self-powered detector in a core reactor according to claim 1, wherein the step of determining the gamma current of the detector to be calibrated due to the gamma effect from the first data set and the second data set comprises the following steps:
by passing
Determining the gamma current generated by the detector to be calibrated due to the gamma effect;
wherein t represents a time after a reactor shutdown operation; i is t Representing the current measured by the detector at time t; t is 1/2 Represents the half-life of the emission material of the probe; i is 0 Representing slow-generating current generated by the detector reacting with neutrons when the reactor is shut down; k represents the gamma effect of the detector during shutdown operation of the reactorThe gamma current generated;
and determining the response time of the detector to be calibrated according to the solved detection formula.
3. The method for calibrating current for a self-powered nuclear reactor core detector of claim 1, further comprising the steps of:
acquiring gamma current generated by a standard detector due to gamma effect and a gamma share of the standard detector according to the steps S1-S3;
acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector,
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
4. The method for calibrating current for a self-powered nuclear reactor core detector as claimed in claim 2, further comprising the steps of:
and obtaining an attenuation current curve of the detector to be calibrated, and when the current difference value of the attenuation current curve at a certain moment and the current difference value of the time corresponding to the detection formula accord with a preset current difference value, and the fitting degree of the attenuation current curve and the curve corresponding to the detection formula accords with a preset fitting degree, determining that the current calibration of the detector to be calibrated is completed.
5. The method for calibrating current of the self-powered core nuclear detector as claimed in claim 4, wherein if the current calibration of the detector to be calibrated is not completed, the method for calibrating current of the self-powered core nuclear detector comprises the following steps:
acquiring a third data set comprising a third current detected by the detector at a third time after the reactor shutdown operation;
wherein the third time is greater than the second time;
and determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data set and the third data set, and determining a new gamma share of the detector to be calibrated.
6. A system for calibrating a current of a self-powered nuclear reactor core detector, comprising: the device comprises a data acquisition module, a gamma current determination module and a data calibration module;
the data acquisition module is used for acquiring a first data set and a second data set detected by the detector to be calibrated;
wherein the first data set includes a first current detected by the detector at a first time during a reactor trip operation; the second data set comprises a second current detected by the detector at a second time after the reactor shutdown operation;
the gamma current determining module is used for determining the gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the second data group;
the data calibration module is used for subtracting the gamma current generated by the detector to be calibrated due to the gamma effect from each current measured by the detector to be calibrated and determining the gamma share of the detector to be calibrated.
7. The system for nuclear self-powered nuclear detector current calibration as claimed in claim 6, wherein said gamma current determination module is particularly adapted to determine the gamma current by
Determining the gamma current generated by the detector to be calibrated due to the gamma effect;
wherein t represents the time after the reactor shutdown operation; i is t Is shown at tCarving the current measured by the detector; t is 1/2 Half-life of the emitting material of the probe; I.C. A 0 Representing slow-generating current generated by the reaction of the detector and neutrons at the shutdown operation moment; k represents a gamma current generated by the detector due to a gamma effect when the reactor is in shutdown operation;
and determining the response time of the detector to be calibrated according to the solved detection formula.
8. The system for calibrating current for self-powered nuclear reactor core detectors of claim 6, wherein the data acquisition module, the gamma current determination module and the data calibration module are invoked to acquire gamma current of a standard detector due to gamma effect and a gamma fraction of the standard detector;
the detector current calibration further comprises a thermal neutron sensitivity module;
the thermal neutron sensitivity module is used for acquiring the relative thermal neutron sensitivity of the detector to be calibrated relative to the standard detector;
and re-determining the new relative thermal neutron sensitivity according to the relative thermal neutron sensitivity, the gamma current generated by the detector to be calibrated due to the gamma effect and the gamma current generated by the standard detector due to the gamma effect.
9. The system for nuclear self-powered probe current calibration of claim 7, wherein said system for nuclear self-powered probe current calibration further comprises a calibration decision;
and the calibration judgment is used for acquiring an attenuation current curve of the detector to be calibrated, and when the current of the attenuation current curve at a certain moment is in accordance with the preset current difference value according to the current difference value of the time corresponding to the detection formula and the fitting degree of the attenuation current curve and the curve corresponding to the detection formula is in accordance with the preset fitting degree, the current calibration of the detector to be calibrated is determined to be completed.
10. The detector core nuclear self-powered detector current calibration system of claim 9, wherein said data acquisition module is further configured to acquire a third data set including a third current detected by said detector at a third time after said reactor shutdown operation;
wherein the third time is greater than the second time;
the gamma current determining module is further used for determining a new gamma current generated by the detector to be calibrated due to the gamma effect according to the first data group and the third data group,
the data calibration module is further used for determining a new gamma share of the detector to be calibrated.
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