CN109192338B - Calibration method for middle range protection fixed value in starting process of nuclear power unit - Google Patents

Calibration method for middle range protection fixed value in starting process of nuclear power unit Download PDF

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CN109192338B
CN109192338B CN201810756744.4A CN201810756744A CN109192338B CN 109192338 B CN109192338 B CN 109192338B CN 201810756744 A CN201810756744 A CN 201810756744A CN 109192338 B CN109192338 B CN 109192338B
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power
value
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intermediate range
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CN109192338A (en
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费瑞银
郭远熊
陈军
于超
郑超雄
孙海山
洪志强
韩超
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Lingao Nuclear Power Co Ltd
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Lingdong Nuclear Power Co Ltd
Lingao Nuclear Power Co Ltd
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Abstract

The invention is suitable for the technical field of reactor control and protection systems, and provides a calibration method of a nuclear power unit starting process intermediate range protection fixed value, which comprises the following steps: acquiring the thermal power of a reactor core and the voltage values of two channels of a middle range; converting the voltage value into a current value according to a voltage-current conversion relation; and calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value. By the method, the protection constant value of the intermediate range of the out-of-reactor nuclear measurement system can be calibrated in the starting process after the pressurized water reactor nuclear power unit is subjected to refueling and overhaul, the determination and adjustment working efficiency of the protection constant value is improved, and the retention time of a low-power platform is shortened.

Description

Calibration method for middle range protection fixed value in starting process of nuclear power unit
Technical Field
The invention belongs to the technical field of reactor control and protection systems, and particularly relates to a calibration method for a nuclear power unit starting process intermediate range protection fixed value.
Background
The intermediate range channel is a component of a nuclear instrumentation system of a reactor and consists of two independent identical lines, ensuring redundant measurement of neutron fluence rates ranging from 2 x 10 to 5 x 10n/cm · s (10% to 100% of rated power). The mid-span measurement line is used when the reactor is critical to 10% of rated power. The protection signal generated by the middle range neutron measurement channel comprises: the locking signal C1 has high neutron fluence rate in the middle range, the fixed value is 20% FP full power, and when the fixed value is exceeded, the locking is performed by automatically or manually controlling the rod to lift; a shutdown signal RT with a high neutron fluence rate in the middle range and a constant value of 25% FP; predicted transient ATWT, without scram, is fixed at 30% FP.
The pressurized water reactor nuclear power generating unit has the accidents of rod ejection, accidental dilution or accidental loss of coolant and the like in the starting process after the nuclear power changing overhaul, so that the power of a reactor is unexpectedly and greatly increased to bring the risk of local burning of a reactor core, a protection signal C1/RT/ATWT needs to be set in the middle range of an out-of-reactor nuclear measurement system to prevent the power of the reactor core from unexpectedly rising too high, different protection signals correspond to the change of the middle range current levels with different power levels, the middle range current corresponding to the power levels changes along with different reactor core loads and different fuel consumption levels, the protection signal cannot act in time, the unit stays on a low-power platform for a long time, and the risk of middle range saturation is easily generated after the nuclear power changing of the unit is restarted.
Disclosure of Invention
In view of this, the embodiment of the invention provides a calibration method for a middle range protection fixed value in a starting process of a nuclear power unit, so as to solve the problems that a protection signal cannot act in time, the unit stays for a long time on a low-power platform, and a middle range saturation risk is easily generated after the nuclear power unit is restarted after refueling.
The first aspect of the embodiment of the invention provides a calibration method for a middle range protection fixed value in a starting process of a nuclear power unit, which comprises the following steps:
acquiring the thermal power of a reactor core and the voltage values of two channels of a middle range;
converting the voltage value into a current value according to a voltage-current conversion relation;
and calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value.
A second aspect of the embodiments of the present invention provides a calibration apparatus for a middle range protection fixed value in a starting process of a nuclear power generating unit, including:
the data acquisition unit is used for acquiring the thermal power of the reactor core and the voltage values of two channels of the middle range;
the conversion unit is used for converting the voltage value into a current value according to a voltage-current conversion relation;
and the calculation unit is used for calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value.
A third aspect of an embodiment of the present invention provides a nuclear power generating set intermediate range protection fixed value calibration system, including: the calibration method comprises a thermal balance measurement device KME, a nuclear instrument RPN device, a universal meter, a memory, a processor and a computer program which is stored in the memory and can run on the processor, wherein the processor realizes the steps of the calibration method for the protection fixed value of the middle good layer of the nuclear power unit when executing the computer program.
A fourth aspect of the embodiment of the present invention provides a computer-readable storage medium, where a computer program is stored, and when the computer program is executed by a processor, the steps of the nuclear power unit intermediate range protection fixed value calibration method are implemented.
Compared with the prior art, the embodiment of the invention has the following beneficial effects: according to the embodiment of the invention, in the starting process of the nuclear power unit, the thermal power of the reactor core and the voltage values of two channels of the middle range are collected, the voltage values are converted into the current values, the current value corresponding to the protection signal of the middle range is calculated according to the thermal power and the current values, and the protection fixed value of the middle range of the nuclear measurement system outside the reactor can be calibrated in the starting process of the pressurized water reactor nuclear power unit after the overhaul of the materials, so that the working efficiency of determining and adjusting the protection fixed value in the starting process is improved, the retention time of the unit on a low-power platform is reduced, and the risk caused by the current saturation of the middle range is reduced.
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In order to more clearly illustrate the technical solutions in the embodiments of the present invention, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.
FIG. 1 is a schematic flow chart illustrating an implementation of a calibration method for an intermediate range protection fixed value in a starting process of a nuclear power generating unit according to an embodiment of the present invention;
FIG. 2 is a schematic diagram of a calibration device for a nuclear power generating unit intermediate range protection fixed value during a starting process according to an embodiment of the invention;
FIG. 3 is a schematic diagram of a calibration system for a nuclear power generating unit intermediate range protection fixed value during startup according to an embodiment of the present invention.
Detailed Description
In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the invention. It will be apparent, however, to one skilled in the art that the present invention may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present invention with unnecessary detail.
It will be understood that the terms "comprises" and/or "comprising," when used in this specification and the appended claims, specify the presence of stated features, integers, steps, operations, elements, and/or components, but do not preclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and/or groups thereof.
It is also to be understood that the terminology used in the description of the invention herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the invention. As used in the specification of the present invention and the appended claims, the singular forms "a," "an," and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise.
It should be further understood that the term "and/or" as used in this specification and the appended claims refers to and includes any and all possible combinations of one or more of the associated listed items.
In order to explain the technical means of the present invention, the following description will be given by way of specific examples.
Referring to fig. 1, the method for calibrating the middle-range protection fixed value in the starting process of the nuclear power unit provided by the embodiment of the invention can calibrate the middle-range protection fixed value in the starting process of the pressurized water reactor nuclear power unit after refueling and overhaul, so that accidents such as rod ejection, accidental dilution or accidental loss of coolant in the starting process are avoided; the protection signal is set in the middle range of the pressurized water reactor to the outer nuclear measurement system, so that the power of the reactor core is prevented from rising unexpectedly and being too high; because the middle-range current corresponding to the power level changes with different reactor core loads and different fuel consumption levels, the protection fixed value of the middle range needs to be calibrated and set again after the pressurized water reactor nuclear power unit reloads each time. The specific calibration method is detailed as follows:
and S101, acquiring the thermal power of the reactor core and the voltage values of two channels of the middle range.
In the present embodiment, the intermediate range includes a plurality of power steps, and the core thermal power and the voltage values of the two channels are different for different power steps. In order to obtain the voltage value and the thermal power value of the reactor core in the middle range under different power steps and ensure the stability of data, the unit to be tested needs to stably operate for at least 2 hours at the corresponding power step, the thermal power of the reactor core is measured by a two-loop thermal balance system KME, and the voltage values of two channels of a main control middle range are measured by a nuclear instrument system RPN.
Further, the acquiring of the thermal power of the reactor core and the voltage values of the two channels of the middle range includes:
at least five voltage values are collected per channel, and an average voltage value of the collected voltage values is calculated.
In the present embodiment, at the time of collecting the voltage values, at least 5 voltage values are collected and recorded per channel or an appropriate 5 values are selected from continuously measured data, and an average value of the 5 voltage values is taken.
And step S102, converting the voltage value into a current value according to the voltage-current conversion relation.
In this embodiment, the protection control signal is directly triggered by the current of the middle range, and the power level of the reactor is used as protection control information for analysis in the safety analysis, so that the power level corresponding to the protection constant value of the middle range of the nuclear power unit is calibrated by the current level of the middle range, and the measured voltage value is converted into a current value.
The current threshold and the voltage threshold corresponding to different nuclear power generating units are different, so that the conversion relation is also different.
Further, the converting the voltage value into the current value according to the voltage-current conversion relationship includes:
the voltage-current conversion relation is I-10-11+0.8*VOr I ═ 10-13+2*V，
Wherein I is a current value and V is a voltage value.
In the present embodiment, the current threshold is 10-11～10-3A, corresponding voltage threshold is 0- +10V or 1- +5V, and corresponding conversion relation is I-10-11+0.8*VOr I ═ 10-13+2*V。
And step S103, calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value.
In this embodiment, the calculation of the current levels corresponding to different power steps is different from the setting criteria, and the protection signal includes: latching signal C1, trip signal RT, anticipated transient signal ATWT failing to scram. Before triggering the intermediate range emergency shutdown, a locking signal C1 is generated firstly, the R rod is automatically locked, and the manual and automatic lifting of the power control is automatically carried out, so that the control rod is prevented from being continuously drawn out to trigger unnecessary shutdown; the shutdown signal RT is used to prevent and limit reactive anomalies in the reactor in sub-critical or low power states from introducing incidents such as: the consequences caused by rod ejection accidents, rod lifting accidents, boron dilution accidents, main steam pipeline breakage accidents and the like; after the predicted transient signal ATWT which can not be stopped urgently is generated, a steam turbine tripping operation, a reactor emergency stop, an auxiliary feed water pump information signal starting, a third group of steam exhaust condenser valves are locked, and a signal that the neutron flux is larger than 30% FP is protected.
The power step of the intermediate range includes: the method comprises the steps of performing zero power test, 8 +/-2% FP power step and 30 +/-2% FP power step before the nuclear power unit is refueled and stopped and before the critical test and before the zero power test.
Further, in the power stage of the zero power test, if the core loading mode and the fuel type do not change greatly, the core is considered to be in a balanced cycle, and in the power stage of the zero power test, the current fixed value corresponding to the protection signal can be the final fixed value of the previous cycle; the unit fuel corresponds to different cycles in different power stages, for example, neutron flux levels are different in the cycle stages corresponding to the initial cycle life and the later stage of the unit fuel, so that current values corresponding to the intermediate range are different.
Because the intermediate range current changes along with different reactor core loads and non-stop burnup levels, if the fuel type and the reactor core loading mode change significantly and the final fixed value of an over-cycle or the previous cycle is not reliable, the current fixed value corresponding to the intermediate range protection signal is calculated according to the thermal power and the current value, and the method comprises the following steps:
calculating a current fixed value corresponding to the intermediate range protection signal after the zero power test is finished according to the current value, wherein the calculation formula is as follows:
Figure BDA0001726891290000061
Figure BDA0001726891290000062
Figure BDA0001726891290000063
wherein i is the channel number of the intermediate range, i is 1, 2, IRCDOPPLER，iThe current value of the ith channel of the intermediate range when the DOPLER point appears in the critical test is 10-6A，
C1iThe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
Further, in a power stage 8 ± 2% FP power stage where the zero power test is completed, the calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value further includes:
calculating a power deviation value corresponding to a middle range protection signal of the power step of 8 +/-2% FP according to the thermal power and the current value;
determining a current fixed value corresponding to the intermediate range protection signal according to the power deviation value;
the deviation value calculation formula is as follows:
Figure BDA0001726891290000064
Figure BDA0001726891290000071
Figure BDA0001726891290000072
wherein, i-1 and 2 represent channel numbers of intermediate range; p is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP;
IRCP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRCC1－old，ithe current corresponding to the channel I (channel C1) of the middle range is set to be a constant value after the zero power test is finished;
IRCRT－old，ithe current corresponding to the channel RT of the middle range I is set after the zero power test is finished;
IRCATWT－old，ithe current corresponding to the channel I ATWT after the zero power test is finished is set;
ΔC1,ithe power deviation value corresponding to the blocking signal of the channel I in the middle range;
ΔRT,ithe power deviation value is corresponding to the shutdown signal of the channel i in the middle range;
ΔATWT,iand the power deviation value corresponds to the predicted transient signal of the channel i at the intermediate range, which is not subjected to emergency shutdown.
Further, the determining a current constant value corresponding to the intermediate range protection signal according to the deviation value includes:
if ΔC1,i|<5% FP and | ΔRT,i|<5% FP and | ΔATWT,i|<5% FP, i 1, 2, then
Figure BDA0001726891290000073
Figure BDA0001726891290000074
Figure BDA0001726891290000075
If ΔC1,i| equal to or greater than 5% FP or | DeltaRT,i| equal to or greater than 5% FP or | DeltaATWT,iFP of | ≧ 5%, i ═ 1, 2, then
Figure BDA0001726891290000081
Figure BDA0001726891290000082
Figure BDA0001726891290000083
Wherein P is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP, IRCP，iThe current value of the channel I of the middle range acquired at the power step of 8 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
Further, in a 30 ± 2% FP power stage of the nuclear power unit, the calculating a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value further includes:
calculating a current fixed value corresponding to a middle range protection signal of a power step of 30 +/-2% FP according to the thermal power and the current value, wherein the calculation formula is as follows:
Figure BDA0001726891290000084
Figure BDA0001726891290000085
Figure BDA0001726891290000086
wherein, i is 1, 2, P8±2％FPThe thermal power collected at the power step of 8 +/-2% FP, the unit is% FP;
P30±2％FPthermal power collected at 30 ± 2% FP power steps in% FP;
IRC8±2％FP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRC30±2％FP，ithe current value of the channel i at the middle range of the power step of 30 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is set;
RTithe current of the shutdown signal corresponding to the ith channel of the intermediate range is set;
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
Further, the calibration method of the intermediate range protection fixed value in the starting process of the nuclear power unit further comprises the following steps: and the protection constant value of the intermediate range before refueling and shutdown to the critical test is the final current constant value corresponding to the last cycle of the reactor core fuel.
In this embodiment, the current constant value corresponding to the intermediate range protection signal from the refueling shutdown to the critical test may be constant in the last cycle.
Further, the calibration method of the intermediate range protection fixed value in the starting process of the nuclear power unit further comprises the following steps:
C1i＝2.0×10-5A，
RTi＝2.5×10-5A，
ATWTisetting a final current value corresponding to the last cycle of the reactor core fuel;
wherein, i is 1 and 2, and represents the ith channel of the intermediate range;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is set;
RTithe current of the shutdown signal corresponding to the ith channel of the intermediate range is set;
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
In this embodiment, after the refueling of the reactor is completed and before the physical test is started to reach the critical test, the current constant values corresponding to the C1 and RT protection signals of the intermediate range of the RPN system of the nuclear instrument need to be adjusted, and the current constant value corresponding to the ATWT protection signal remains unchanged.
It should be noted that, within the technical scope of the present disclosure, other sequencing schemes that can be easily conceived by those skilled in the art should also be within the protection scope of the present disclosure, and detailed description is omitted here.
According to the embodiment, in the starting process of the nuclear power unit, the voltage values of the thermal power of the reactor core and the voltage values of two channels of the middle range are collected, the voltage values are converted into the current values, the current values corresponding to the middle range protection signals are calculated according to the thermal power and the current values, the protection fixed value of the middle range of the nuclear power unit outside the reactor can be calibrated in the starting process after the pressurized water reactor nuclear power unit is subjected to refueling overhaul, the working efficiency of determining and adjusting the protection fixed value in the starting process is improved, the retention time of the nuclear power unit on a low-power platform is reduced, and the risk caused by the current saturation of the middle range is reduced; by the embodiment, the determination and adjustment work of the related fixed value of 48% FP is cancelled, the heat efficiency of a second loop of the system equipment is improved, the power-up time of 48% FP platform is saved after each overhaul, and the risk caused by the possible saturation of the intermediate range is reduced.
It should be understood that, the sequence numbers of the steps in the foregoing embodiments do not imply an execution sequence, and the execution sequence of each process should be determined by its function and inherent logic, and should not constitute any limitation to the implementation process of the embodiments of the present invention.
Fig. 2 is a schematic diagram of a calibration apparatus for a nuclear power generating unit intermediate range protection fixed value during a starting process according to an embodiment of the present invention, and for convenience of description, only parts related to the embodiment of the present invention are shown.
The calibration device for the middle range protection fixed value in the starting process of the nuclear power unit comprises:
the data acquisition unit 21 is used for acquiring the thermal power of the reactor core and the voltage values of two channels of the middle range;
a conversion unit 22 for converting the voltage value into a current value according to a voltage-current conversion relationship;
and the calculating unit 23 is configured to calculate a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value.
According to the embodiment, in the starting process of the nuclear power unit, the voltage values of the thermal power of the reactor core and the voltage values of two channels of the middle range are collected, the voltage values are converted into the current values, the current values corresponding to the middle range protection signals are calculated according to the thermal power and the current values, the protection fixed value of the middle range of the nuclear power unit outside the reactor can be calibrated in the starting process after the pressurized water reactor nuclear power unit is subjected to refueling overhaul, the working efficiency of determining and adjusting the protection fixed value in the starting process is improved, the retention time of the nuclear power unit on a low-power platform is reduced, and the risk caused by the current saturation of the middle range is reduced; by the embodiment, the determination and adjustment work of the related fixed value of 48% FP is cancelled, the heat efficiency of a second loop of the system equipment is improved, the power-up time of 48% FP platform is saved after each overhaul, and the risk caused by the possible saturation of the intermediate range is reduced.
It will be apparent to those skilled in the art that, for convenience and simplicity of description, the foregoing division of the functional modules is merely illustrated, and in practical applications, the above function distribution may be performed by different functional units and modules as needed, that is, the internal structure of the mobile terminal is divided into different functional units or modules to perform all or part of the above described functions. Each functional module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional modules are only used for distinguishing one functional module from another, and are not used for limiting the protection scope of the application. The specific working process of the module in the mobile terminal may refer to the corresponding process in the foregoing method embodiment, and is not described herein again.
Fig. 3 is a schematic diagram of a calibration system for a nuclear power generating unit intermediate range protection fixed value in a starting process according to an embodiment of the present invention. As shown in fig. 3, the calibration system 3 for the intermediate range protection fixed value in the starting process of the nuclear power generating unit of the embodiment includes: a thermal balance measuring device KME, a nuclear gauge RPN device, a multimeter, a processor 30, a memory 31 and a computer program 32 stored in said memory 31 and executable on said processor 30, wherein the multimeter supports a voltage class of 10V, with a tolerance of ± 0.01V, and the multimeter can also be another recorder fulfilling the same accuracy. When the processor 30 executes the computer program 32, the steps in the above embodiments of the nuclear power generating unit intermediate range protection fixed value calibration method, such as the steps 101 to 103 shown in fig. 1, are implemented. Alternatively, the processor 30, when executing the computer program 32, implements the functions of the modules/units in the above-mentioned device embodiments, such as the functions of the modules 21 to 24 shown in fig. 2.
Illustratively, the computer program 32 may be partitioned into one or more modules/units that are stored in the memory 31 and executed by the processor 30 to implement the present invention. The one or more modules/units may be a series of computer program instruction segments capable of performing specific functions, and the instruction segments are used for describing the execution process of the computer program 32 in the calibration system 3 for the nuclear power unit starting process intermediate range protection fixed value.
The calibration system 3 for the nuclear power generating unit middle range protection constant value in the starting process can include, but is not limited to, a processor 30 and a memory 31. It will be understood by those skilled in the art that fig. 3 is only an example of the calibration system 3 for the intermediate range protection constant value in the starting process of the nuclear power generating unit, and does not constitute a limitation to the calibration system 3 for the intermediate range protection constant value in the starting process of the nuclear power generating unit, and may include more or less components than those shown in the drawings, or may combine some components, or different components, for example, the calibration system 3 for the intermediate range protection constant value in the starting process of the nuclear power generating unit may further include an input-output device, a network access device, a bus, and the like.
The Processor 30 may be a Central Processing Unit (CPU), other general purpose Processor, a Digital Signal Processor (DSP), an Application Specific Integrated Circuit (ASIC), an off-the-shelf Programmable Gate Array (FPGA) or other Programmable logic device, discrete Gate or transistor logic, discrete hardware components, etc. A general purpose processor may be a microprocessor or the processor may be any conventional processor or the like.
The memory 31 may be an internal storage unit of the calibration system 3 for the nuclear power unit starting process intermediate range protection fixed value, for example, a hard disk or a memory of the calibration system 3 for the nuclear power unit starting process intermediate range protection fixed value. The memory 31 may also be an external storage device of the calibration system 3 for the middle range protection fixed value in the starting process of the nuclear power unit, for example, a plug-in hard disk, an intelligent memory Card (Smart Media Card, SMC), a Secure Digital (SD) Card, a Flash memory Card (Flash Card), and the like, which are equipped on the calibration system 3 for the middle range protection fixed value in the starting process of the nuclear power unit. Further, the memory 31 may also include both an internal storage unit and an external storage device of the calibration system 3 for the nuclear power generating unit starting process intermediate range protection fixed value. The memory 31 is used for storing the computer program and other programs and data required by the calibration system 3 for the intermediate range protection fixed value in the starting process of the nuclear power generating unit. The memory 31 may also be used to temporarily store data that has been output or is to be output.
It will be apparent to those skilled in the art that, for convenience and brevity of description, only the above-mentioned division of the functional units and modules is illustrated, and in practical applications, the above-mentioned function distribution may be performed by different functional units and modules according to needs, that is, the internal structure of the apparatus is divided into different functional units or modules to perform all or part of the above-mentioned functions. Each functional unit and module in the embodiments may be integrated in one processing unit, or each unit may exist alone physically, or two or more units are integrated in one unit, and the integrated unit may be implemented in a form of hardware, or in a form of software functional unit. In addition, specific names of the functional units and modules are only for convenience of distinguishing from each other, and are not used for limiting the protection scope of the present invention. The specific working processes of the units and modules in the system may refer to the corresponding processes in the foregoing method embodiments, and are not described herein again.
In the above embodiments, the descriptions of the respective embodiments have respective emphasis, and reference may be made to the related descriptions of other embodiments for parts that are not described or illustrated in a certain embodiment.
Those of ordinary skill in the art will appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware or combinations of computer software and electronic hardware. Whether such functionality is implemented as hardware or software depends upon the particular application and design constraints imposed on the implementation. Skilled artisans may implement the described functionality in varying ways for each particular application, but such implementation decisions should not be interpreted as causing a departure from the scope of the present invention.
In the embodiments provided in the present invention, it should be understood that the disclosed apparatus/terminal device and method may be implemented in other ways. For example, the above-described embodiments of the apparatus/terminal device are merely illustrative, and for example, the division of the modules or units is only one logical division, and there may be other divisions when actually implemented, for example, a plurality of units or components may be combined or integrated into another system, or some features may be omitted, or not executed. In addition, the shown or discussed mutual coupling or direct coupling or communication connection may be an indirect coupling or communication connection through some interfaces, devices or units, and may be in an electrical, mechanical or other form.
The units described as separate parts may or may not be physically separate, and parts displayed as units may or may not be physical units, may be located in one place, or may be distributed on a plurality of network units. Some or all of the units can be selected according to actual needs to achieve the purpose of the solution of the embodiment.
In addition, functional units in the embodiments of the present invention may be integrated into one processing unit, or each unit may exist alone physically, or two or more units are integrated into one unit. The integrated unit can be realized in a form of hardware, and can also be realized in a form of a software functional unit.
The integrated modules/units, if implemented in the form of software functional units and sold or used as separate products, may be stored in a computer readable storage medium. Based on such understanding, all or part of the flow of the method according to the embodiments of the present invention may also be implemented by a computer program, which may be stored in a computer-readable storage medium, and when the computer program is executed by a processor, the steps of the method embodiments may be implemented. Wherein the computer program comprises computer program code, which may be in the form of source code, object code, an executable file or some intermediate form, etc. The computer-readable medium may include: any entity or device capable of carrying the computer program code, recording medium, usb disk, removable hard disk, magnetic disk, optical disk, computer Memory, Read-Only Memory (ROM), Random Access Memory (RAM), electrical carrier wave signals, telecommunications signals, software distribution medium, and the like. It should be noted that the computer readable medium may contain other components which may be suitably increased or decreased as required by legislation and patent practice in jurisdictions, for example, in some jurisdictions, computer readable media which may not include electrical carrier signals and telecommunications signals in accordance with legislation and patent practice.
The above-mentioned embodiments are only used for illustrating the technical solutions of the present invention, and not for limiting the same; although the present invention has been described in detail with reference to the foregoing embodiments, it will be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present invention, and are intended to be included within the scope of the present invention.

Claims (7)

1. A calibration method for a middle range protection fixed value in the starting process of a nuclear power unit is characterized by comprising the following steps:
gather the voltage value of two passageways of reactor core thermal power and middle range, include:
after the unit to be tested stably operates for at least 2 hours at the corresponding power step, measuring the thermal power of the reactor core through a two-loop thermal balance system KME, and measuring the voltage values of two channels of a main control intermediate range through a nuclear instrument system RPN;
converting the voltage value into a current value according to a voltage-current conversion relationship, including:
the voltage-current conversion relation is I-10-11+0.8*VOr I ═ 10-13+2*V，
Wherein I is a current value, and V is a voltage value;
calculating a current constant value corresponding to a middle range protection signal according to the thermal power and the current value, wherein the current constant value corresponding to the middle range protection signal comprises: the current constant value corresponding to the locking signal C1, the current constant value corresponding to the shutdown signal RT and the current constant value corresponding to the predicted transient signal ATWT which can not be subjected to emergency shutdown;
the current constant value corresponding to the intermediate range protection signal is calculated according to the thermal power and the current value, and the method comprises the following steps:
calculating a current fixed value corresponding to the intermediate range protection signal after the zero power test is finished according to the current value, wherein the calculation formula is as follows:
Figure FDA0002491959060000011
Figure FDA0002491959060000012
Figure FDA0002491959060000021
wherein i is the channel number of the intermediate range, i is 1, 2, IRCDOPPLER，iThe current value of the ith channel of the intermediate range when the DOPLER point appears in the critical test is 10-6A，
C1iThe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to make emergency shutdown is set;
calculating a power deviation value corresponding to a middle range protection signal of the power step of 8 +/-2% FP according to the thermal power and the current value;
determining a current constant value corresponding to the intermediate range protection signal according to the power deviation value, wherein the current constant value comprises the following steps:
if ΔC1,i|<5% FP and | ΔRT,i|<5% FP and | ΔATWT,i|<5% FP, i 1, 2, then
Figure FDA0002491959060000022
Figure FDA0002491959060000023
Figure FDA0002491959060000024
If ΔC1,i| equal to or greater than 5% FP or | DeltaRT,i| equal to or greater than 5% FP or | DeltaATWT,iFP of | ≧ 5%, i ═ 1, 2, then
Figure FDA0002491959060000031
Figure FDA0002491959060000032
Figure FDA0002491959060000033
Wherein P is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP, IRCP，iThe current value of the channel I of the middle range acquired at the power step of 8 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to make emergency shutdown is set;
the deviation value calculation formula is as follows:
Figure FDA0002491959060000034
Figure FDA0002491959060000035
Figure FDA0002491959060000036
wherein, i-1 and 2 represent channel numbers of intermediate range; p is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP;
IRCP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRCC1－old，ithe current corresponding to the channel I (channel C1) of the middle range is set to be a constant value after the zero power test is finished;
IRCRT－old，ithe current corresponding to the channel RT of the middle range I is set after the zero power test is finished;
IRCATWT－old，ithe current corresponding to the channel I ATWT after the zero power test is finished is set;
ΔC1,ithe power deviation value corresponding to the blocking signal of the channel I in the middle range;
ΔRT,ithe power deviation value is corresponding to the shutdown signal of the channel i in the middle range;
ΔATWT,ithe power deviation value is corresponding to an estimated transient signal of the channel i with the intermediate range, wherein the estimated transient signal cannot be subjected to emergency shutdown;
calculating a current fixed value corresponding to a middle range protection signal of a power step of 30 +/-2% FP according to the thermal power and the current value, wherein the calculation formula is as follows:
Figure FDA0002491959060000041
Figure FDA0002491959060000042
Figure FDA0002491959060000043
wherein, i is 1, 2, P8±2％FPThe thermal power collected at the power step of 8 +/-2% FP, the unit is% FP;
P30±2％FPthermal power collected at 30 ± 2% FP power steps in% FP;
IRC8±2％FP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRC30±2％FP，ithe current value of the channel i at the middle range of the power step of 30 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is set;
RTithe current of the shutdown signal corresponding to the ith channel of the intermediate range is set;
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
2. The method for calibrating the middle-range protection constant value in the starting process of the nuclear power generating unit as claimed in claim 1, wherein the step of collecting the thermal power of the reactor core and the voltage values of two channels of the middle range comprises the following steps:
at least five voltage values are collected per channel, and an average voltage value of the collected voltage values is calculated.
3. The method for calibrating the intermediate range protection constant value in the starting process of the nuclear power generating unit as claimed in claim 1, wherein the method further comprises:
and the protection constant value of the intermediate range before refueling and shutdown to the critical test is the final current constant value corresponding to the last cycle of the reactor core fuel.
4. The method for calibrating the intermediate range protection constant value in the starting process of the nuclear power generating unit as claimed in claim 1, wherein the method further comprises:
the middle range protection constant values before the reactor is reloaded to the critical test are respectively as follows:
C1i＝2.0×10-5A，
RTi＝2.5×10-5A，
ATWTisetting a final current value corresponding to the last cycle of the reactor core fuel;
wherein, i is 1 and 2, and represents the ith channel of the intermediate range;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is set;
RTithe current of the shutdown signal corresponding to the ith channel of the intermediate range is set;
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
5. The utility model provides a calibration device of range protection definite value in middle of nuclear power unit start-up process which characterized in that includes:
the data acquisition unit is used for gathering the voltage value of two passageways of reactor core thermal power and middle range, includes:
after the unit to be tested stably operates for at least 2 hours at the corresponding power step, measuring the thermal power of the reactor core through a two-loop thermal balance system KME, and measuring the voltage values of two channels of a main control intermediate range through a nuclear instrument system RPN;
a conversion unit for converting the voltage value into a current value according to a voltage-current conversion relationship, comprising:
the voltage-current conversion relation is I-10-11+0.8*VOr I ═ 10-13+2*V，
Wherein I is a current value, and V is a voltage value;
a calculating unit, configured to calculate a current constant value corresponding to the intermediate range protection signal according to the thermal power and the current value, where the current constant value corresponding to the intermediate range protection signal includes: the current constant value corresponding to the locking signal C1, the current constant value corresponding to the shutdown signal RT and the current constant value corresponding to the predicted transient signal ATWT which can not be subjected to emergency shutdown;
the current constant value corresponding to the intermediate range protection signal is calculated according to the thermal power and the current value, and the method comprises the following steps:
calculating a current fixed value corresponding to the intermediate range protection signal after the zero power test is finished according to the current value, wherein the calculation formula is as follows:
Figure FDA0002491959060000071
Figure FDA0002491959060000072
Figure FDA0002491959060000073
wherein i is the channel number of the intermediate range, i is 1, 2, IRCDOPPLER，iThe current value of the ith channel of the intermediate range when the DOPLER point appears in the critical test is 10-6A，
C1iThe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to make emergency shutdown is set;
calculating a power deviation value corresponding to a middle range protection signal of the power step of 8 +/-2% FP according to the thermal power and the current value;
determining a current constant value corresponding to the intermediate range protection signal according to the power deviation value, wherein the current constant value comprises the following steps:
if ΔC1,i|<5% FP and | ΔRT,i|<5% FP and | ΔATWT,i|<5% FP, i 1, 2, then
Figure FDA0002491959060000081
Figure FDA0002491959060000082
Figure FDA0002491959060000083
If ΔC1,i| equal to or greater than 5% FP or | DeltaRT,i| equal to or greater than 5% FP or | DeltaATWT,iFP of | ≧ 5%, i ═ 1, 2, then
Figure FDA0002491959060000084
Figure FDA0002491959060000085
Figure FDA0002491959060000086
Wherein P is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP, IRCP，iThe current value of the channel I of the middle range acquired at the power step of 8 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is constant,
RTithe current constant value of the shutdown signal corresponding to the ith channel of the intermediate range,
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to make emergency shutdown is set;
the deviation value calculation formula is as follows:
Figure FDA0002491959060000091
Figure FDA0002491959060000092
Figure FDA0002491959060000093
wherein, i-1 and 2 represent channel numbers of intermediate range; p is the thermal power collected at the power step of 8 +/-2% FP, and the unit is% FP;
IRCP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRCC1－old，ithe current corresponding to the channel I (channel C1) of the middle range is set to be a constant value after the zero power test is finished;
IRCRT－old，ithe current corresponding to the channel RT of the middle range I is set after the zero power test is finished;
IRCATWT－old，ithe current corresponding to the channel I ATWT after the zero power test is finished is set;
ΔC1,ithe power deviation value corresponding to the blocking signal of the channel I in the middle range;
ΔRT,ithe power deviation value is corresponding to the shutdown signal of the channel i in the middle range;
ΔATWT,ithe power deviation value is corresponding to an estimated transient signal of the channel i with the intermediate range, wherein the estimated transient signal cannot be subjected to emergency shutdown;
calculating a current fixed value corresponding to a middle range protection signal of a power step of 30 +/-2% FP according to the thermal power and the current value, wherein the calculation formula is as follows:
Figure FDA0002491959060000101
Figure FDA0002491959060000102
Figure FDA0002491959060000103
wherein, i is 1, 2, P8±2％FPThe thermal power collected at the power step of 8 +/-2% FP, the unit is% FP;
P30±2％FPis at 30 + -2% FThermal power collected by the P power step, unit% FP;
IRC8±2％FP，ithe current value of the channel i is the intermediate range of the power step of 8 +/-2 percent FP;
IRC30±2％FP，ithe current value of the channel i at the middle range of the power step of 30 +/-2 percent FP;
C1ithe current of the locking signal corresponding to the ith channel of the intermediate range is set;
RTithe current of the shutdown signal corresponding to the ith channel of the intermediate range is set;
ATWTithe current of the predicted transient signal which is corresponding to the ith channel of the intermediate range and fails to scram is fixed.
6. A nuclear power generating unit intermediate range protection constant value calibration system, which comprises a thermal balance measuring device KME, a nuclear instrument RPN device, a universal meter, a memory, a processor and a computer program stored in the memory and capable of running on the processor, wherein the steps of the method according to any one of claims 1 to 4 are realized when the processor executes the computer program.
7. A computer-readable storage medium, in which a computer program is stored which, when being executed by a processor, carries out the steps of the method according to any one of claims 1 to 4.
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