CN112599264A - Method for accurately positioning position of control rod - Google Patents
Method for accurately positioning position of control rod Download PDFInfo
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- CN112599264A CN112599264A CN202011417508.3A CN202011417508A CN112599264A CN 112599264 A CN112599264 A CN 112599264A CN 202011417508 A CN202011417508 A CN 202011417508A CN 112599264 A CN112599264 A CN 112599264A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/12—Sensitive element forming part of control element
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
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Abstract
The invention discloses a control rod position accurate positioning method.A control rod position accurate positioning calculation module is arranged in a rod position measuring cabinet, the control rod position accurate positioning calculation module records rod position signal reference information in the control rod lifting process through pre-calculation, and the rod position signal and reference data are compared and calculated in normal operation so as to obtain the accurate position of a control rod of each measuring channel. The method for accurately positioning the position of the control rod has the advantages that the full-stroke positioning accuracy can reach +/-2 steps, the positioning result can be directly transmitted to a DCS (digital control System) of a whole plant in a communication mode, and the out-of-step monitoring of the rod position can be carried out on the basis of the method, so that the out-of-step alarm can be triggered before the out-of-step of the control rod reaches 5 steps; the rod bundles with normal lifting positions are not needed after the step-out alarm occurs, the direct lifting of the step-out rod bundles for realignment does not introduce large reactive disturbance, and the reactive change during the step-out correction period is prevented from being compensated by adjusting the boron concentration.
Description
Technical Field
The invention belongs to the technical field of nuclear power station control rod position measurement, and particularly relates to a control rod position accurate positioning method.
Background
The fast regulation of reactor power in pressurized water reactor nuclear power plants is mainly achieved by controlling the lifting and downward insertion of the rod bundles. The control operations of lifting, inserting and the like of the rod bundle are finished under the command of a rod control system.
However, existing rod control systems do not themselves include a feedback mechanism for verifying that the rod cluster control commands have been properly executed. Therefore, a rod position measuring system is required to be arranged, the actual position of the rod cluster is obtained through the rod position measuring system, the operation condition of the rod control system is monitored, and the accurate positioning of the rod cluster is controlled.
Referring to fig. 1, taking the second nuclear power plant in the mountains of the Qinshan as an example, the core equipment of the conventional rod position measuring system includes 33 rod position detectors, 2 measuring cabinets, 1 processing cabinet and 1 rod position display screen (including 33 rod position display modules). The rod position detector is positioned above a reactor top control rod driving mechanism in the containment, the measuring cabinet and the distribution cabinet are positioned in an electrical factory building 15.5m L609/649 room, the processing cabinet is positioned in a connecting factory building 0m W228/268 room, and the rod position display screen is positioned in a main control room. The measuring cabinet is used for providing a primary coil excitation power supply of the detector, and reshaping induced voltage signals of the measuring coil to obtain rod position gray code signals, on one hand, the rod position gray code signals are sent to the processing cabinet for comparison and processing, on the other hand, the rod position gray code signals are translated into binary codes, and the binary codes are sent to the main control room for display after being subjected to photoelectric isolation.
The existing rod cluster control assembly and a driving shaft thereof are positioned in a high-temperature and high-pressure environment of a nuclear reactor, and the position of the rod cluster control assembly is measured by a rod position detector by generally utilizing an electromagnetic induction principle. The existing rod position detector mainly comprises a primary coil, a measuring coil, an auxiliary coil, a coil framework, a sealing shell and an outer sleeve.
Taking the second nuclear power plant in Qinshan as an example, the overall length of the rod position detector is 4006mm, the inner diameter is 154mm, and the outer diameter is 300 mm. The primary coil is a long solenoid, about 2000 turns, with a wire diameter of 1.97mm, and is wound along the entire stroke. The measuring coil and the auxiliary coil are secondary side coils, each of which has 1700 turns, 2cm width and 0.23mm wire diameter and is coaxial with the primary side coil. The primary coil is used for generating an alternating magnetic field, the measuring coil is used for forming a rod position code, and the auxiliary coil is used for primary current regulation.
The drive shaft is made of magnetic material, and the permeability of the sealing shell, the framework, the outer sleeve and other media in the detector is low, so that the voltage induced by the drive shaft passing through the measuring coil is greatly different, and the top end or the bottom end of the drive shaft can be known by monitoring the induced voltage of the measuring coil at a certain position. The position of the drive shaft, the control rod, can be determined substantially by monitoring the induced voltage signal of each coil, provided that a sufficient number of measurement coils are provided.
In order to substantially determine the position of the control rod, a sufficient number of measuring coils must be provided. The number and spacing of the measurement coils is determined based on the length of the drive shaft stroke and the desired resolution. In order to reduce the number of connections between the detectors and the signal processing channels, and the number of signal processing devices, the measurement coils must also be grouped.
Taking the second nuclear power plant in Qinshan as an example, the length of each mechanical step of the control rod driving shaft is 15.875mm, and the full stroke is 228 steps. The detector resolution was 8 steps (127mm), 31 measurement coils were divided into A, B, C, D, E five groups, and the total measurement stroke was 256 mechanical steps. The measurement coils are grouped as follows.
First, if a measuring coil C1 is wound at 1/2 of the measuring stroke of the probe, it is known whether the rod position is in the [0, 128 ] interval or the [128, 256 ] interval by monitoring the induced voltage (effective value, the same applies hereinafter) V1.
Further, if the coils C21 and C22 are wound at the heights of 1/4 and 3/4, the rod position can be known to be in a [0, 64) interval or a [64, 128) interval by monitoring the induced voltage V21 of the C21; by monitoring the induced voltage V22 of C22, it can be known whether the rod position is in the [128, 192) interval or the [192, 256) interval.
In fact, the three coils divide the whole measuring stroke into four intervals with equal length, and the induced voltage of the three coils is monitored to know which interval the rod position is in; the induced voltage levels and corresponding rod positions can be tabulated below.
If C21 and C22 are connected in series in reverse to form a group (called C2), because V21 and V22 are always in phase, the output voltage V2 of C2 is | V21-V22 |, and the induction voltage is low and the corresponding rod position is shown in the following table.
Similarly, four coils of C31, C32, C33 and C34 are wound at the heights of 1/8, 3/8, 5/8 and 7/8 and are sequentially connected in series in a positive-negative mode to form a C3 group, so that the whole measuring stroke can be divided into 8 intervals with equal length, and the interval in which the rod beam is located can be determined by monitoring three voltages of V1, V2 and V3 (i.e., | V31-V32 + V33-V34 |), and the measuring resolution reaches 32 steps.
And then eight coils C41, C42, … and C48 are wound at the heights of 1/16, 3/16, 5/16, 7/16, 9/16, 11/16, 13/16 and 15/16, and are connected in series in a positive-negative mode to form a C4 group, so that the whole measuring stroke can be divided into 16 intervals with equal length, and the interval in which the rod beam is located can be determined by monitoring four voltages V1, V2, V3 and V4 (i.e. | V41-V42 + V43 … -V48 |), and the measuring resolution reaches 16 steps.
And then sixteen coils C51, C52, … and C516 are wound at the heights of 1/32, 3/32, 5/32, … and 31/32 and are sequentially connected in series in a positive-negative mode to form a C5 group, so that the whole measuring stroke can be divided into 32 intervals with equal length, and the interval in which the rod bundle is positioned can be determined by monitoring five voltages V1, V2, V3, V4 and V5 (i.e. | V51-V52 + V53 … -V516 |), and the measuring resolution reaches 8 steps.
The C1, C2, C3, C4 and C5 groups are generally referred to as E, D, C, B, A groups, respectively, and the coils are numbered from low to high, so that the coils in each group are numbered as:
group E (first group) of coils 16
Group D (second group) coil 824
Group C (third group) coil 4122028
Group B (fourth group) coil 26101418222630
Group a (fifth group) coil 135791113151719212325272931
The detector structure and coil numbering refer to figure 2.
The induced voltage signals of each group of measuring coils of the rod position detector change along with the lifting stroke of the control rod, and the rod position measuring method is generally characterized in that the induced voltage of the measuring coils is processed in a rod position measuring cabinet, and the processed voltage is compared with a shaping threshold voltage, so that a rod position code bit of switching value is formed, and the rod position code bit is shown in an attached figure 3. The bar position measurement results obtained for different shaping threshold voltages vary, see fig. 4.
Thus, through threshold setting, the control rod position is converted into 5-bit Gray codes, 32 code values are provided, each code value corresponds to a position interval with the length of 8 mechanical steps, the theoretical rod position measurement error is +/-4 steps, and actually, certain error exists due to signal processing and threshold setting, and the actual rod position measurement precision is +/-6- +/-8 steps.
Referring to fig. 5 (taking the second nuclear power plant in the Qinshan as an example), in order to ensure uniform power distribution of the reactor, the control rods are symmetrically arranged in the reactor core, 4 control rods (except for the central rod cluster) in each subgroup are respectively positioned in 4 quadrants, the 4 control rods are always lifted and lowered simultaneously, in order to prevent the positions of the 4 rod clusters in the same subgroup from being inconsistent due to the failure of a control rod driving mechanism or other reasons, the actual position deviation of the 4 rod clusters is monitored, and when the deviation exceeds 1 measuring position, a rod out-of-step alarm is triggered to prompt an operator to realign the rod positions.
Because the stick position measurement accuracy is not high, cause following two aspects influences:
firstly, control rod positioning accuracy can not ensure: if the rod position measurement accuracy is +/-6 steps, even if the two control rods are at the same measurement position, the actual rod positions may have 12 steps of difference; in fact, because the control rods cannot be completely synchronized in the lifting process, the control rods cannot be judged to be out-of-step when the difference between the control rods is 1, and an alarm can be triggered only when the difference between the control rods is 2 or more, at this time, the actual rod positions may have a difference of 20 steps (considering that the rod 1 is at the bottom of the nth interval, the actual position may be 8n-6, the rod 2 is at the top of the n +1 interval, the actual position may be 8(n +1) +6, and the difference between the two is 20 steps);
secondly, the operation of adjusting alignment after the step loss is found to be complex: after the step is lost, because the actual rod position deviation cannot be determined, all the rod bundles need to be inserted into the next indicator lamp to be just lighted and then lifted again, and the negative reactivity introduced in the process needs to be compensated by operations such as boron regulation and the like, and the reference is made to fig. 6.
Disclosure of Invention
Aiming at the condition of the prior art, the invention overcomes the defects and provides a method for accurately positioning the position of a control rod.
The invention discloses a method for accurately positioning the position of a control rod, which mainly aims to ensure that the full-stroke positioning precision can reach +/-2 steps, a positioning result can be directly transmitted to a DCS (digital control system) of a whole factory in a communication mode, and the out-of-step monitoring of the rod position can be carried out on the basis of the positioning result to trigger out-of-step alarm before the out-of-step of the control rod reaches 5 steps; the rod bundles with normal lifting positions are not needed after the step-out alarm occurs, the direct lifting of the step-out rod bundles for realignment does not introduce large reactive disturbance, and the reactive change during the step-out correction period is prevented from being compensated by adjusting the boron concentration.
The invention discloses a method for accurately positioning the position of a control rod, and the method is also used for acquiring the accurate position of the control rod from a rod position measuring signal while realizing the whole digitalization of a rod position measuring signal processing mode, thereby improving the rod position monitoring precision and simplifying the step-out alignment operation.
The invention discloses a method for accurately positioning the position of a control rod, which is further used for carrying out comparison calculation on a rod position signal and reference data to obtain the position of the control rod during normal operation by pre-calculating and recording rod position signal reference information in the lifting process of the control rod.
The invention discloses a control rod position accurate positioning method, and the other purpose is to arrange a control rod position accurate positioning calculation module in a rod position measurement cabinet, wherein the control rod position accurate positioning calculation module has a control rod position accurate positioning calculation function.
The invention discloses a method for accurately positioning the position of a control rod, which is characterized in that a control rod position accurate positioning calculation module is arranged in a rod position measurement cabinet, the control rod position accurate positioning calculation module records rod position signal reference information in the lifting process of the control rod through pre-calculation, and the rod position signal is compared with reference data in normal operation to obtain the accurate position of the control rod of each measurement channel, and the method comprises the following steps:
step S1: after the nuclear reactor is started to reach a thermal shutdown working condition, lifting and inserting all control rods for one stroke, capturing the control rod action condition of each measuring channel in the process, and calculating and recording rod position characteristic information when judging that the control rods act;
step S2: storing a reference signal array after the lifting step number reaches a complete lifting stroke;
step S3: capturing a control rod action signal during normal operation, calculating a rod position characteristic signal when the control rod is judged to have action, and comparing and analyzing a calculation result with a reference signal array;
step S4: the rod position processing cabinet or the whole-plant digital instrument control system performs comparative analysis on the accurately calculated rod position, and outputs out-of-step alarm when the deviation threshold is exceeded;
step S5: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position is observed, if the step-out rod cluster is abnormal, the rod position measuring system is repaired, and if the step-out rod cluster is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
According to the above aspect, as a further preferable aspect of the above aspect:
step S1 is embodied as the following steps:
after the nuclear reactor is started and reaches the thermal shutdown working condition, all control rods are lifted and inserted for one stroke, the action condition of the control rods of each measuring channel is captured in the process, and when the control rods are judged to act:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil;
step S3 is embodied as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil;
c) calculating the deviation between the current signal and the reference signal array of each step of the '6-225-5 step method' according to the matching factor;
d) and taking the position with the minimum error as an accurate calculation rod position.
According to the above aspect, as a further preferable aspect of the above aspect:
step S1 is embodied as the following steps:
after the nuclear reactor is started to reach a thermal shutdown working condition, all the measurement channels are switched to a self-setting operation mode through button operation, under the self-setting operation mode, lifting and inserting operation is carried out on all the subgroup control rods, 4 groups of control rods of each subgroup simultaneously act, lifting is carried out from 5 steps to the top of the reactor, then the control rods are inserted back to 5 steps, the action condition of the control rods of all the measurement channels is automatically captured in the process, and when the control rods act, the control rods are judged:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) and calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil.
According to the above aspect, as a further preferable aspect of the above aspect:
step S3 is embodied as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil;
d) calculating the deviation between 21 characteristic values of the current signals Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue and the reference value arrays of each step according to the matching factors;
e) and taking the index of the reference value array with the minimum error, obtaining the accurate calculation rod position according to the index, and marking as PosCalc.
According to the above aspect, as a further preferable aspect of the above aspect:
step S4 is specifically implemented as: and the rod position PosCalc accurately calculated by each rod bundle is transmitted to a rod position processing cabinet or a digital instrument control system of the whole plant in a communication mode for comparison and analysis, and an out-of-step alarm is output when the deviation threshold value is exceeded.
According to the above aspect, as a further preferable aspect of the above aspect:
step S5 is specifically implemented as: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position PosCalc is observed, if the rod position PosCalc is abnormal, the rod position measuring system is repaired, and if the rod position PosCalc is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
According to the above aspect, as a further preferable aspect of the above aspect:
the calculation method of step d) in step S3 includes the step of obtaining the deviation array enWherein n is 0.439:
1) setting n to be 0;
2) calculating Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud, P.Ue and a reference array Uaxn、Ubxn、Ucxn、Udxn、Uexn、……、P.Udn、P.UenAnd (4) obtaining an absolute value of the deviation to obtain a deviation vector:
(|Uax-Uaxn|,|Ubx-Ubxn|,|Ucx-Ucxn|,|Udx-Udxn|,|Uex-Uexn|
……|P.Ud-P.Udn|,|P.Ue-P.Uen|)；
3) performing dot product operation on the deviation vector and the matching factor vector to obtain a deviation enIf the matching factor vector is (1,1,1,1, 0,0,0,0,0,0,0,0,0,0,0,0), the corresponding deviation is calculated as:
deviation en＝|Uax-Uaxn|+|Ubx-Ubxn|+|Ucx-Ucxn|+|Udx-Udxn|+|Uex-Uexn|；
4) Setting n as n + 1;
5) if n <440, continue with steps 2), 3), 4).
According to the above aspect, as a further preferable aspect of the above aspect:
the calculation method in step e) of step S3 is as follows:
1) find the array en(n ═ 0..439), with subscript m;
2) if m is less than 220, PosCalc is 6+ m;
and if m is more than or equal to 220, PosCalc is 444-m.
According to the above aspect, as a further preferable aspect of the above aspect:
the comparative analysis method of step S4 is as follows:
1) calculating the maximum value Max and the minimum value Min of the rod positions PosCalc of all the rod bundles in all the rod groups Sa, A, B, C and D;
2) and if the Max-Min is greater than 4, triggering an alarm.
According to the above aspect, as a further preferable aspect of the above aspect:
the step of recovering from step S5 is as follows:
1) the mode selection switch is set to 'out-of-step correction 1';
2) placing the bar group selection switch in the out-of-step deviation bar group (one of Sa, A, B, C and D);
3) setting the out-of-step correction calculator to zero;
4) inhibiting the non-faulty bundle in the bundle from moving;
5) the 'out-of-step correction effective switch' is turned to an effective position;
6) monitoring the fault rod cluster to accurately calculate the rod position PosCalc, inserting (for example, PosCalc is more than or equal to 7) or lifting the fault rod cluster for 1-2 steps, and confirming that the PosCalc changes correspondingly in each step;
7) if the PosCalc does not have corresponding change, the repair rod position measuring system is informed;
8) if the rod position is normal, lifting or inserting the fault rod cluster until the accurately calculated rod position PosCalc is consistent with the accurately calculated rod positions of other rod clusters in the rod group;
9) the mode selection switch is set to "manual" or "automatic", and the correction operation is ended.
The method for accurately positioning the position of the control rod has the advantages that the full-stroke positioning accuracy can reach +/-2 steps, the positioning result can be directly transmitted to a DCS (digital control System) of a whole plant in a communication mode, and the out-of-step monitoring of the rod position can be carried out on the basis of the positioning result, so that the out-of-step alarm can be triggered before the out-of-step of the control rod reaches 5 steps; the rod bundles with normal lifting positions are not needed after the step-out alarm occurs, the direct lifting of the step-out rod bundles for realignment does not introduce large reactive disturbance, and the reactive change during the step-out correction period is prevented from being compensated by adjusting the boron concentration.
Drawings
FIG. 1 is a system block diagram of a rod position measurement system.
FIG. 2 is a schematic diagram of a rod position detector coil arrangement and connection.
FIG. 3 is a schematic diagram of a rod position detector measurement signal shaping process.
FIG. 4 is a schematic diagram of setting threshold voltage changes resulting in measurement endpoint shifts.
FIG. 5 is a view of the arrangement of the control bundles of the second nuclear power plant in Qinshan mountains in the core.
Wherein, the number of the control rod bundles is 33, and the control rod bundles are divided into nine subgroups; a1, A2, B1, B2, C1, C2 and D are power adjusting rod groups, and SA1 and SA2 are shutdown rod groups; c2 has only one bundle of rods and each of the remaining subgroups has 4 bundles of rods.
Fig. 6 is a schematic view showing an example of the step-out bundle correction manner.
FIG. 7 is a flow chart of the method for accurately positioning the position of the control stick according to the preferred embodiment of the present invention.
FIG. 8 is a flow chart of the precise rod position calculation of the preferred embodiment of the present invention.
In which the adjustment of boron concentration to compensate for reactivity variations during step-out correction is substantially avoided by the above step-out alignment operation, but care may be taken in particular cases to maintain the primary average temperature in line with the reference average temperature by changing the boron concentration or by appropriately changing the steam turbine load.
FIG. 9 is a flow chart of the step-out bundle correction of the preferred embodiment of the present invention.
FIG. 10 is a schematic diagram of an example of control stick position pinpoint waveform matching in accordance with a preferred embodiment of the present invention.
FIG. 11 is a schematic diagram of an example of control stick position accurate positioning data matching in accordance with a preferred embodiment of the present invention.
Detailed Description
The invention discloses a method for accurately positioning the position of a control rod, and the specific implementation mode of the invention is further described by combining the preferred embodiment.
It is worth mentioning that fig. 1 shows a system block diagram of the rod position measuring system; FIG. 2 illustrates a rod position detector coil arrangement and connection; FIG. 3 illustrates a rod position detector measurement signal shaping process; FIG. 4 illustrates that setting threshold voltage changes result in measurement endpoint shifts; FIG. 5 illustrates a layout of a Qinshan second nuclear power plant control cluster in a core; FIG. 6 shows an example of an out-of-sync rod cluster correction mode; FIG. 7 shows a flow chart of a control stick position pinpointing method according to a preferred embodiment of the present invention; FIG. 8 illustrates a precise rod position calculation flow of a preferred embodiment of the present invention; FIG. 9 illustrates an out-of-step cluster correction flow of a preferred embodiment of the present invention; FIG. 10 illustrates an example of control stick position pinpoint waveform matching in accordance with a preferred embodiment of the present invention; FIG. 11 shows an example of control stick position accurate positioning data matching in accordance with a preferred embodiment of the present invention.
It is worth mentioning that in fig. 5 of the drawings, the number of control bundles is 33, and the control bundles are divided into nine subgroups; a1, A2, B1, B2, C1, C2 and D are power adjusting rod groups, and SA1 and SA2 are shutdown rod groups; c2 has only one bundle of rods and each of the remaining subgroups has 4 bundles of rods.
It is worth mentioning that in fig. 6 of the drawings, note 1: during the rod dropping process, the boron concentration or the proper change of the steam engine load is adopted to maintain the average dimension of the primary circuit consistent with the reference average temperature.
It is worth mentioning that in fig. 9 of the drawings, note: the use of the above out-of-step leveling operation substantially avoids the need to adjust the boron concentration to compensate for reactivity variations during out-of-step correction, but care may be taken in particular situations where changing the boron concentration or changing the steam turbine load appropriately to maintain the primary average temperature consistent with the reference average temperature.
It should be noted that, in the embodiments of the present invention, a "6-225-5 steps method" may be involved, and we define that, after a complete lifting trip of the second nuclear power plant in the Qinshan mountain, the data is sorted to form 440 sets of reference data, and the array elements 0 to 439 correspond to 6-225-5 steps, respectively.
Preferred embodiments.
Referring to FIG. 1 of the drawings, a rod position measurement system 100 includes a rod position measurement cabinet 20, the rod position measurement cabinet 20 providing excitation power to a rod position detector 10.
It should be noted that the control rod position measurement position is obtained by the present invention without using the traditional threshold value setting method, but a control rod position precise positioning calculation module 21 is built in the rod position measurement cabinet 20, and the control rod position precise positioning calculation module 21 has a (integrated) control rod position precise positioning function.
Specifically, the method for accurately positioning the position of the control rod includes the following steps (see fig. 7 of the accompanying drawings) that a control rod position accurate positioning calculation module 21 is arranged in a rod position measurement cabinet 20, the control rod position accurate positioning calculation module 21 records rod position signal reference information in the control rod lifting process through pre-calculation, and the rod position signal is compared with reference data in normal operation to obtain the accurate position of the control rod of each measurement channel, wherein the control rod position accurate positioning calculation module 21 includes:
step S1: after the nuclear reactor is started to reach a thermal shutdown working condition, lifting and inserting all control rods for one stroke, capturing the control rod action condition of each measuring channel in the process, and calculating and recording rod position characteristic information when judging that the control rods act;
step S2: storing a reference signal array after the lifting step number reaches a complete lifting stroke;
step S3: capturing a control rod action signal during normal operation, calculating a rod position characteristic signal when the control rod is judged to have action, and comparing and analyzing a calculation result with a reference signal array;
step S4: the rod position processing cabinet 30 or the whole-plant digital instrument control system 50 carries out comparative analysis on the accurately calculated rod position, and outputs out-of-step alarm when the deviation threshold value is exceeded;
step S5: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position is observed, if the change condition is abnormal, the rod position measuring system 100 is repaired, and if the change condition is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
It is worth mentioning that, the control rod position accurate positioning method disclosed by the patent application of the invention has the advantages that the full stroke positioning accuracy can reach +/-2 steps, the positioning result can be directly transmitted to a factory digital instrument control system DCS in a communication mode, and the rod position out-of-step monitoring can be carried out on the basis of the positioning result, so that out-of-step alarm can be triggered before the control rod out-of-step reaches 5 steps; the rod bundles with normal lifting positions are not needed after the step-out alarm occurs, the direct lifting of the step-out rod bundles for realignment does not introduce large reactive disturbance, and the reactive change during the step-out correction period is prevented from being compensated by adjusting the boron concentration.
The following is a first implementation of the preferred embodiment.
Further, step S1 is specifically implemented as the following steps:
after the nuclear reactor is started and reaches the thermal shutdown working condition, all control rods are lifted and inserted for one stroke, the action condition of the control rods of each measuring channel is captured in the process, and when the control rods are judged to act:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) and calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil.
Further, step S3 is specifically implemented as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil;
c) calculating the deviation between the current signal and the reference signal array of each step of the '6-225-5 step method' according to the matching factor;
d) and taking the position with the minimum error as an accurate calculation rod position.
Further, in step S5, when the out-of-step alarm occurs, the out-of-step stick bundle is preferably inserted by 2 steps.
The following is a second implementation of the preferred embodiment.
Further, step S1 is specifically implemented as the following steps:
after the nuclear reactor is started to reach a thermal shutdown working condition, all the measurement channels are switched to a self-setting operation mode through button operation, under the self-setting operation mode, lifting and inserting operation is carried out on all the subgroup control rods, each subgroup of 4-bundle control rod simultaneously acts, the control rods are lifted to the top of the reactor from 5 steps (generally 225 steps), and then the control rods are inserted back to 5 steps, in the process, the action condition of the control rods of all the measurement channels is automatically captured, and when the control rods act, the control rods are judged:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) and calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil.
Further, step S2 is specifically implemented as: storing a reference signal array after the number of lifting steps reaches a complete lifting stroke (the data are sorted into 440 groups of reference data after a complete lifting stroke of a second nuclear power plant in Qinshan, and the array elements 0-439 correspond to 6-225-5 steps respectively);
further, step S3 is specifically implemented as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil;
d) calculating the deviation between 21 characteristic values of the current signals Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue and the reference value arrays of each step according to the matching factors;
e) and taking the index of the reference value array with the minimum error, obtaining the accurate calculation rod position according to the index, and marking as PosCalc.
Further, step S4 is specifically implemented as: and the rod position PosCalc accurately calculated by each rod bundle is transmitted to the rod position processing cabinet 30 or the digital instrument control system 50 of the whole plant in a communication mode for comparison and analysis, and an out-of-step alarm is output when the deviation threshold value is exceeded.
Further, step S5 is specifically implemented as: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position PosCalc is observed, if the change condition is abnormal, the rod position measuring system 100 is repaired, and if the change condition is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
It should be noted that in step S1, the calculation of the reference value record of each step only needs to be performed once during the debugging or overhaul of the hot state, unless the rod position detector 10 is replaced.
Further, referring to fig. 8 of the drawings, taking the second nuclear power plant in the Qin mountain as an example, the calculation method of step d) in the step S3 includes the following steps to obtain the deviation array enWherein n is 0.439:
5) setting n to be 0;
6) calculating Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud, P.Ue and a reference array Uaxn、Ubxn、Ucxn、Udxn、Uexn、……、P.Udn、P.UenAnd (4) obtaining an absolute value of the deviation to obtain a deviation vector:
(|Uax-Uaxn|,|Ubx-Ubxn|,|Ucx-Ucxn|,|Udx-Udxn|,|Uex-Uexn|……|P.Ud-P.Udn|,|P.Ue-P.Uen|)；
7) performing dot product operation on the deviation vector and the matching factor vector to obtain a deviation enIf the matching factor vector is (1,1,1,1, 0,0,0,0,0,0,0,0,0,0,0,0), the corresponding deviation is calculated as:
deviation en＝|Uax-Uaxn|+|Ubx-Ubxn|+|Ucx-Ucxn|+|Udx-Udxn|+|Uex-Uexn|；
8) Setting n as n + 1;
9) if n <440, continue with steps 2), 3), 4).
Further, taking the second nuclear power plant in the Qin mountain as an example, the calculation method in step e) of step S3 is as follows:
3) find the array en(n ═ 0..439), with subscript m;
4) if m is less than 220, PosCalc is 6+ m;
5) and if m is more than or equal to 220, PosCalc is 444-m.
Further, taking the second nuclear power plant in the Qin mountain as an example, the comparative analysis method in the step S4 is as follows:
2) calculating the maximum value Max and the minimum value Min of the rod positions PosCalc of all the rod bundles in all the rod groups Sa, A, B, C and D;
3) and if the Max-Min is greater than 4, triggering an alarm.
Further, referring to fig. 9 of the drawings, taking the second nuclear power plant in the mountains of the qin as an example, the step of recovering from step S5 is as follows:
9) the mode selection switch is set to 'out-of-step correction 1';
10) placing the bar group selection switch in the out-of-step deviation bar group (one of Sa, A, B, C and D);
11) setting the out-of-step correction calculator to zero;
12) inhibiting the non-faulty bundle in the bundle from moving;
13) the 'out-of-step correction effective switch' is turned to an effective position;
14) monitoring the fault rod cluster to accurately calculate the rod position PosCalc, inserting (for example, PosCalc is more than or equal to 7) or lifting the fault rod cluster for 1-2 steps, and confirming that the PosCalc changes correspondingly in each step;
15) if the PosCalc does not have corresponding change, the repair rod position measuring system is informed;
16) if the rod position is normal, lifting or inserting the fault rod cluster until the accurately calculated rod position PosCalc is consistent with the accurately calculated rod positions of other rod clusters in the rod group;
17) the mode selection switch is set to "manual" or "automatic", and the correction operation is ended.
Note: the use of the above out-of-step leveling operation substantially avoids the need to adjust the boron concentration to compensate for reactivity variations during out-of-step correction, but care may be taken in particular situations where changing the boron concentration or changing the steam turbine load appropriately to maintain the primary average temperature consistent with the reference average temperature.
According to various implementations of the above preferred embodiments, an example of control stick position pinpoint waveform matching is shown in FIG. 10 of the drawings; an example of control stick position accurate positioning data matching is shown in figure 11 of the accompanying drawings.
It should be noted that technical features such as specific types of selection switches related to the present patent application should be regarded as the prior art, specific structures, operation principles, control modes and spatial arrangement modes of the technical features may be selected conventionally in the field, and should not be regarded as the points of the present patent, and the present patent is not further specifically described in detail.
It will be apparent to those skilled in the art that modifications and equivalents may be made in the embodiments and/or portions thereof without departing from the spirit and scope of the present invention.
Claims (10)
1. A control rod position accurate positioning method is characterized in that a control rod position accurate positioning calculation module is arranged in a rod position measuring cabinet, the control rod position accurate positioning calculation module records rod position signal reference information in the control rod lifting process through pre-calculation, and the rod position signal and reference data are compared and calculated in normal operation to obtain the accurate position of a control rod of each measuring channel, and the method comprises the following steps:
step S1: after the nuclear reactor is started to reach a thermal shutdown working condition, lifting and inserting all control rods for one stroke, capturing the control rod action condition of each measuring channel in the process, and calculating and recording rod position characteristic information when judging that the control rods act;
step S2: storing a reference signal array after the lifting step number reaches a complete lifting stroke;
step S3: capturing a control rod action signal during normal operation, calculating a rod position characteristic signal when the control rod is judged to have action, and comparing and analyzing a calculation result with a reference signal array;
step S4: the rod position processing cabinet or the whole-plant digital instrument control system performs comparative analysis on the accurately calculated rod position, and outputs out-of-step alarm when the deviation threshold is exceeded;
step S5: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position is observed, if the step-out rod cluster is abnormal, the rod position measuring system is repaired, and if the step-out rod cluster is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
2. The method for accurately positioning control rod positions as set forth in claim 1, wherein:
step S1 is embodied as the following steps:
after the nuclear reactor is started and reaches the thermal shutdown working condition, all control rods are lifted and inserted for one stroke, the action condition of the control rods of each measuring channel is captured in the process, and when the control rods are judged to act:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil;
step S3 is embodied as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current of a primary coil, the voltage of the primary coil, the voltage of an auxiliary coil and the voltages of five groups of measuring coils of the rod position detector after each step of action;
b) calculating the ratio of the voltage of the auxiliary coil to the current of the primary coil, and calculating the voltage of the primary coil, the voltage of the auxiliary coil and the phase difference between the voltage of the five groups of measuring coils and the current of the primary coil;
c) calculating the deviation between the current signal and the reference signal array of each step of the '6-225-5 step method' according to the matching factor;
d) and taking the position with the minimum error as an accurate calculation rod position.
3. The method for accurately positioning control rod positions as set forth in claim 1, wherein:
step S1 is embodied as the following steps:
after the nuclear reactor is started to reach a thermal shutdown working condition, all the measurement channels are switched to a self-setting operation mode through button operation, under the self-setting operation mode, lifting and inserting operation is carried out on all the subgroup control rods, 4 groups of control rods of each subgroup simultaneously act, lifting is carried out from 5 steps to the top of the reactor, then the control rods are inserted back to 5 steps, the action condition of the control rods of all the measurement channels is automatically captured in the process, and when the control rods act, the control rods are judged:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) and calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil.
4. The method of claim 3, wherein:
step S3 is embodied as the following steps:
capturing a control rod action signal during normal operation, and judging that the control rod has action:
a) calculating and recording the current Ip of a primary coil, the voltage Up of the primary coil, the voltage Uaux of an auxiliary coil and the voltage Ua/Ub/Uc/Ud/Ue of five groups of measuring coils after each step of action;
b) calculating the ratio Uaux/Ip of the auxiliary coil voltage to the primary coil current, and calculating five groups of measurement coil voltage correction values Uax, Ua/Ip, Ubx Ub/Ip, Ucx Uc/Ip, Udx Ud/Ip and Uex Ue/Ip;
c) calculating the phase differences P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue between the voltage of the primary coil, the voltage of the auxiliary coil and the current of the primary coil;
d) calculating the deviation between 21 characteristic values of the current signals Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud and P.Ue and the reference value arrays of each step according to the matching factors;
e) and taking the index of the reference value array with the minimum error, obtaining the accurate calculation rod position according to the index, and marking as PosCalc.
5. The method of claim 4, wherein:
step S4 is specifically implemented as: and the rod position PosCalc accurately calculated by each rod bundle is transmitted to a rod position processing cabinet or a digital instrument control system of the whole plant in a communication mode for comparison and analysis, and an out-of-step alarm is output when the deviation threshold value is exceeded.
6. The method of claim 5, wherein:
step S5 is specifically implemented as: and (3) when the step-out alarm occurs, the step-out rod cluster is operated for 1-2 steps, the change condition of the accurately calculated rod position PosCalc is observed, if the rod position PosCalc is abnormal, the rod position measuring system is repaired, and if the rod position PosCalc is normal, the step-out rod cluster is lifted or inserted until the accurately calculated rod position is consistent with other rod clusters.
7. The control rod position accurate positioning method according to any one of claims 4 to 6, characterized in that:
the calculation method of step d) in step S3 includes the step of obtaining the deviation array enWherein n is 0.439:
1) setting n to be 0;
2) calculating Uax, Ubx, Ucx, Udx, Uex, Ua, Ub, Uc, Ud, Ue, Ip, Up, Uaux/Ip, Uaux, P.Up, P.Uaux, P.Ua, P.Ub, P.Uc, P.Ud, P.Ue and a reference array Uaxn、Ubxn、Ucxn、Udxn、Uexn、……、P.Udn、P.UenAnd (4) obtaining an absolute value of the deviation to obtain a deviation vector:
(|Uax-Uaxn|,|Ubx-Ubxn|,|Ucx-Ucxn|,|Udx-Udxn|,|Uex-Uexn|
……|P.Ud-P.Udn|,|P.Ue-P.Uen|)；
3) performing dot product operation on the deviation vector and the matching factor vector to obtain a deviation enIf the matching factor vector is (1,1,1,1, 0,0,0,0,0,0,0,0,0,0,0,0), the corresponding deviation is calculated as:
deviation en＝|Uax-Uaxn|+|Ubx-Ubxn|+|Ucx-Ucxn|+|Udx-Udxn|+|Uex-Uexn|；
4) Setting n as n + 1;
5) if n <440, continue with steps 2), 3), 4).
8. The method of claim 7, wherein:
the calculation method in step e) of step S3 is as follows:
1) find the array en(n ═ 0..439), with subscript m;
2) if m is less than 220, PosCalc is 6+ m;
and if m is more than or equal to 220, PosCalc is 444-m.
9. The method of claim 8, wherein:
the comparative analysis method of step S4 is as follows:
1) calculating the maximum value Max and the minimum value Min of the rod positions PosCalc of all the rod bundles in all the rod groups Sa, A, B, C and D;
2) and if the Max-Min is greater than 4, triggering an alarm.
10. The method for accurately positioning control rod positions as set forth in claim 9, wherein:
the step of recovering from step S5 is as follows:
1) the mode selection switch is set to 'out-of-step correction 1';
2) placing the bar group selection switch in the out-of-step deviation bar group (one of Sa, A, B, C and D);
3) setting the out-of-step correction calculator to zero;
4) inhibiting the non-faulty bundle in the bundle from moving;
5) the 'out-of-step correction effective switch' is turned to an effective position;
6) monitoring the fault rod cluster to accurately calculate the rod position PosCalc, inserting (for example, PosCalc is more than or equal to 7) or lifting the fault rod cluster for 1-2 steps, and confirming that the PosCalc changes correspondingly in each step;
7) if the PosCalc does not have corresponding change, the repair rod position measuring system is informed;
8) if the rod position is normal, lifting or inserting the fault rod cluster until the accurately calculated rod position PosCalc is consistent with the accurately calculated rod positions of other rod clusters in the rod group;
9) the mode selection switch is set to "manual" or "automatic", and the correction operation is ended.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114038584A (en) * | 2021-09-26 | 2022-02-11 | 中广核研究院有限公司 | Reactor control system, control rod resetting system and method |
| CN114203007A (en) * | 2021-12-14 | 2022-03-18 | 三门核电有限公司 | Rod position coding card fault simulation system and troubleshooting system |
| WO2023216663A1 (en) * | 2022-05-12 | 2023-11-16 | 中核核电运行管理有限公司 | Method and apparatus for determining rod position of control rod of pressurized water reactor, and rod position measurement system |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5229066A (en) * | 1991-08-05 | 1993-07-20 | Westinghouse Electric Corp. | Control rod position indication system |
| JP2000227490A (en) * | 1999-02-05 | 2000-08-15 | Hitachi Ltd | Control rod drive mechanism |
| CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
| WO2013110410A2 (en) * | 2012-01-27 | 2013-08-01 | Areva Gmbh | Apparatus and method for measuring the position of a displaceable control rod |
| CN104332200A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Monitoring method for synchronism loss of control rods |
| CN107256729A (en) * | 2017-07-20 | 2017-10-17 | 中国核动力研究设计院 | A kind of rod position measurement method based on independent lines ring type stick location probe |
| CN107799194A (en) * | 2017-10-20 | 2018-03-13 | 中核核电运行管理有限公司 | Intelligent rod position threshold value is adjusted and Performance Testing method |
| CN107833643A (en) * | 2017-10-16 | 2018-03-23 | 中核核电运行管理有限公司 | Totally digitilized rod position measuring device and its method |
| WO2020186776A1 (en) * | 2019-03-15 | 2020-09-24 | 中广核核电运营有限公司 | Nuclear power plant reactor control rod addressing apparatus and method |
-
2020
- 2020-12-05 CN CN202011417508.3A patent/CN112599264B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5229066A (en) * | 1991-08-05 | 1993-07-20 | Westinghouse Electric Corp. | Control rod position indication system |
| JP2000227490A (en) * | 1999-02-05 | 2000-08-15 | Hitachi Ltd | Control rod drive mechanism |
| CN101840737A (en) * | 2009-09-02 | 2010-09-22 | 中广核工程有限公司 | Digital rod position control system and method |
| WO2013110410A2 (en) * | 2012-01-27 | 2013-08-01 | Areva Gmbh | Apparatus and method for measuring the position of a displaceable control rod |
| CN104332200A (en) * | 2013-07-22 | 2015-02-04 | 中国核动力研究设计院 | Monitoring method for synchronism loss of control rods |
| CN107256729A (en) * | 2017-07-20 | 2017-10-17 | 中国核动力研究设计院 | A kind of rod position measurement method based on independent lines ring type stick location probe |
| CN107833643A (en) * | 2017-10-16 | 2018-03-23 | 中核核电运行管理有限公司 | Totally digitilized rod position measuring device and its method |
| CN107799194A (en) * | 2017-10-20 | 2018-03-13 | 中核核电运行管理有限公司 | Intelligent rod position threshold value is adjusted and Performance Testing method |
| WO2020186776A1 (en) * | 2019-03-15 | 2020-09-24 | 中广核核电运营有限公司 | Nuclear power plant reactor control rod addressing apparatus and method |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114038584A (en) * | 2021-09-26 | 2022-02-11 | 中广核研究院有限公司 | Reactor control system, control rod resetting system and method |
| CN114038584B (en) * | 2021-09-26 | 2024-05-10 | 中广核研究院有限公司 | Reactor control system, control rod resetting system and method |
| CN114203007A (en) * | 2021-12-14 | 2022-03-18 | 三门核电有限公司 | Rod position coding card fault simulation system and troubleshooting system |
| CN114203007B (en) * | 2021-12-14 | 2024-04-09 | 三门核电有限公司 | Bar code card fault simulation system and fault investigation system |
| WO2023216663A1 (en) * | 2022-05-12 | 2023-11-16 | 中核核电运行管理有限公司 | Method and apparatus for determining rod position of control rod of pressurized water reactor, and rod position measurement system |
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