CN115016409A - Nuclear power station thermal balance verification device and method - Google Patents
Nuclear power station thermal balance verification device and method Download PDFInfo
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Abstract
The invention relates to a nuclear power station thermal balance verification device and a method, comprising the following steps: the system comprises a multi-path distribution module, a data acquisition module and an operation processing verification module; the multi-path distribution module is connected with the transmitter and used for distributing signals transmitted by the transmitter; the data acquisition module is connected with the multi-path distribution module and is used for acquiring signals transmitted by the multi-path distribution module and transmitting the signals to the operation processing verification module; the operation processing and verifying module is connected with the data acquisition module and is used for calculating the thermal power of the reactor core of the acquired data sent by the data acquisition module so as to generate and display a thermal power report of the reactor core. The invention can calculate the thermal power of the reactor core in real time, can check the data processing process in real time, and has good portability and low cost.
Description
Technical Field
The invention relates to the technical field of thermal power measurement verification of a nuclear power plant reactor core and adjustment of thermal balance test parameters in a debugging and starting stage, in particular to a device and a method for verifying thermal balance of a nuclear power plant.
Background
The thermal power of the reactor core of the nuclear power unit is a reference standard of various control protection parameters of the first loop and the second loop, and is a basis for setting the power of a turbine generator unit of a nuclear power plant, and the rapid and accurate measurement of the thermal power of the reactor core of the nuclear power unit is an effective guarantee for the safe and economic operation of the nuclear power unit. If the measured value of the thermal power is lower than the actual value, serious nuclear safety accidents such as serious accidents of overheating of a reactor core, burning of fuel cladding and the like can be caused; if the measured value of the thermal power is higher than the actual value, the steam turbine generator unit cannot be increased to the rated power, and the economical efficiency of the nuclear power unit is seriously affected.
A thermal balance test data acquisition system (KME system for short) is a system for thermal balance calculation of a nuclear power plant, and is required to be capable of accurately measuring the thermal power of a reactor core, but internal algorithm packaging is not disclosed, so that the condition that partial parameters are set incorrectly and measured inaccurately exists, and the calculation result needs to be verified by a thermal balance verification system.
In addition, in the process of debugging the nuclear power unit, some key reactor control and protection parameters need to be checked and adjusted through a thermal balance test, and the method mainly comprises a first loop measurement channel adjustment test, a second loop measurement channel adjustment test, a loop temperature channel check test, a steam and water supply flow check test, a power control and calibration test under a reactor-following machine mode, a coolant flow measurement under a reference thermal load, an evaporator liquid level control under a high flow and a water supply flow control test, wherein the test processes have high requirements on the thermal balance stable operation of the unit, and the loop temperature channel check test even needs the loop temperature fluctuation control within the range of +/-0.2 ℃. The thermal power calculation error built in the nuclear power plant DCS system is large, and the state of the unit needs to be judged by accurate real-time thermal power. If the thermal power change trend of the reactor core can be obtained, the stability of the reactor core can be accurately judged, the stable operation time of the unit is shortened, the efficiency of relevant tests after the unit is critical is improved, and the risk of out-of-control transient test is reduced.
At present, the existing heat balance calculating device of the nuclear power plant can only calculate to obtain a heat power result, can not display and judge trends, can not calculate the real-time heat power of a reactor core, has poor portability, adopts a packaging form for process data and an algorithm, can not check an intermediate processing process, and has high price and high economic cost.
Disclosure of Invention
The invention provides a device and a method for verifying the thermal balance of a nuclear power plant, aiming at the defects of the prior art.
The technical scheme adopted by the invention for solving the technical problems is as follows: a nuclear power plant thermal balance verification apparatus is constructed, including: the system comprises a multi-path distribution module, a data acquisition module and an operation processing verification module;
the multi-path distribution module is connected with the transmitter and used for distributing signals transmitted by the transmitter;
the data acquisition module is connected with the multi-path distribution module and is used for acquiring signals transmitted by the multi-path distribution module and transmitting the signals to the operation processing verification module;
the operation processing verification module is connected with the data acquisition module and is used for calculating the thermal power of the reactor core of the acquired data sent by the data acquisition module so as to generate and display a thermal power report of the reactor core.
In the nuclear power plant thermal balance verification device, the operation processing verification module is further configured to perform uncertainty calculation according to the acquired data sent by the data acquisition module to obtain uncertainty.
In the apparatus for verifying a thermal balance of a nuclear power plant according to the present invention, the demultiplexing module includes: a multi-channel signal conversion resistance plate;
the multi-channel signal conversion resistance plate is connected with the transmitter and used for carrying out multi-channel distribution on the signals transmitted by the transmitter.
In the nuclear power plant thermal balance verification apparatus according to the present invention, the multi-path signal conversion resistance plate includes: a plurality of measurement channels, each of the measurement channels comprising one or more high precision resistors.
In the apparatus for verifying a thermal balance of a nuclear power plant according to the present invention, the data acquisition module includes: an analog-to-digital converter and a multiplexer card;
the multiplexing card is connected with the multi-path distribution module and is used for collecting signals transmitted by the multi-path distribution module;
the analog-to-digital converter is connected with the multiplexing card and is used for performing analog-to-digital conversion on the signals acquired by the multiplexing card.
The invention also provides a nuclear power station thermal balance verification method, which comprises the following steps:
the data acquisition module is used for acquiring signals transmitted by the multi-path distribution module and transmitting the signals to the operation processing verification module;
the operation processing verification module receives the acquired data sent by the data acquisition module;
and the operation processing verification module is used for calculating the thermal power of the reactor core according to the acquired data so as to generate and display a thermal power report of the reactor core.
In the method for verifying the thermal balance of the nuclear power station, the calculation processing verification module calculates the thermal power of the reactor core according to the collected data to generate a thermal power report of the reactor core and displays the report, and the method comprises the following steps:
the operation processing verification module acquires the acquired data according to preset acquisition time and a preset acquisition period;
calculating the thermal power of the reactor core by adopting a first data processing method to obtain the thermal power of the historical reactor core;
or, the second data processing method is adopted to calculate the thermal power of the reactor core, and the real-time thermal power of the reactor core and/or the historical thermal power of the reactor core are/is obtained.
In the method for verifying the thermal balance of the nuclear power plant, the method further includes:
drawing a curve according to the historical reactor core to obtain a historical power curve;
or drawing a curve according to the real-time reactor core thermal power to obtain a real-time power curve.
In the method for verifying the thermal balance of the nuclear power plant according to the present invention, the calculating the thermal power of the core by using the first data processing method to obtain the historical thermal power of the core includes:
acquiring historical data according to the preset acquisition time and the preset acquisition period; the historical data comprises m groups of collected data;
correcting the m groups of collected data to obtain m groups of corrected data;
performing primary screening on m data of each signal to obtain primary screening data;
performing secondary screening on the primary screening data to obtain secondary screening data;
judging whether the bad value rejection rate of the secondary screening data is greater than a threshold value;
if yes, carrying out reliability analysis;
and if not, carrying out mean value processing on the secondary screening data to obtain a historical engineering measured value.
In the method for verifying the thermal balance of the nuclear power plant, the step of screening m data of each signal once to obtain primary screened data includes:
carrying out mean processing on the m data of each signal to obtain a first mean value;
performing standard deviation calculation on the m data of each signal to obtain a first standard deviation value;
and removing bad values according to the first average value and the first standard deviation value to obtain the primary screening data.
In the method for verifying the thermal balance of the nuclear power plant, the secondary screening of the primary screening data to obtain secondary screening data includes:
carrying out mean value processing on the primary screening data to obtain a second mean value;
calculating the standard deviation of the primary screening data to obtain a second standard deviation value;
and removing bad values according to the second average value and the second standard deviation value to obtain the secondary screening data.
In the method for verifying the thermal balance of the nuclear power plant according to the present invention, the calculating the thermal power of the core by using the first data processing method to obtain the historical thermal power of the core further includes:
calculating heat balance flow according to the historical engineering measured value and by combining with instrument pipelines and fluid characteristic parameters to obtain a historical heat balance flow value;
and performing heat balance test calculation according to the historical heat balance flow value and by combining a calculation formula of the core thermal power to obtain the historical core thermal power.
In the method for verifying the thermal balance of the nuclear power plant according to the present invention, the calculating the thermal power of the core by using the second data processing method to obtain the real-time thermal power of the core and/or the historical thermal power of the core includes:
acquiring real-time data according to the preset acquisition time and the preset acquisition period;
correcting the real-time data to obtain a real-time engineering measurement value;
calculating the heat balance flow according to the real-time engineering measured value and by combining instrument pipelines and fluid characteristic parameters to obtain a real-time heat balance flow value;
and performing heat balance test calculation according to the real-time heat balance flow value and by combining a calculation formula of the reactor core thermal power to obtain the real-time reactor core thermal power.
In the method for verifying the thermal balance of the nuclear power plant according to the present invention, the calculating the thermal power of the core by using the second data processing method to obtain the real-time thermal power of the core and/or the historical thermal power of the core includes:
acquiring m groups of data according to the preset acquisition time and the preset acquisition period;
correcting the m groups of data to obtain m groups of engineering measured values;
performing heat balance flow calculation according to the m groups of engineering measured values and by combining instrument pipelines and fluid characteristic parameters to obtain m groups of heat balance flow values;
performing heat balance test calculation according to the m groups of heat balance flow values and by combining a calculation formula of the reactor core thermal power to obtain m groups of reactor core thermal power; and the m groups of reactor core thermal power are the historical reactor core thermal power.
In the method for verifying the thermal balance of the nuclear power plant, the method further includes:
carrying out average calculation on the m groups of heat balance flow values to obtain a process quantity average value;
performing average calculation on the thermal powers of the m groups of reactor cores to obtain the average value of the thermal powers of the reactor cores;
and calculating according to the average value of the thermal power of the reactor core to obtain comprehensive uncertainty.
The nuclear power station heat balance verification device and the method have the following beneficial effects: the method comprises the following steps: the system comprises a multi-path distribution module, a data acquisition module and an operation processing verification module; the multi-path distribution module is connected with the transmitter and used for distributing signals transmitted by the transmitter; the data acquisition module is connected with the multi-path distribution module and is used for acquiring signals transmitted by the multi-path distribution module and transmitting the signals to the operation processing verification module; the operation processing and verifying module is connected with the data acquisition module and is used for calculating the thermal power of the reactor core of the acquired data sent by the data acquisition module so as to generate and display a thermal power report of the reactor core. The invention can calculate the real-time thermal power of the reactor core, can check the data processing process in real time, and has good portability and low cost.
Drawings
The invention will be further described with reference to the accompanying drawings and examples, in which:
FIG. 1 is a schematic structural diagram of a nuclear power plant thermal balance verification apparatus provided in an embodiment of the present invention;
fig. 2 is a schematic diagram of a multi-path signal conversion resistor board provided by an embodiment of the invention;
fig. 3 is a schematic connection diagram of a multi-path signal conversion resistor board provided by an embodiment of the present invention;
FIG. 4 is a schematic flow chart of a first embodiment of a verification method for nuclear power plant thermal equilibrium according to the present invention;
FIG. 5 is a schematic flow chart of a second embodiment of the verification method for the thermal balance of the nuclear power plant according to the present invention;
FIG. 6 is a schematic flow chart of a third embodiment of the verification method for the thermal balance of the nuclear power plant according to the present invention;
FIG. 7 is a schematic flow chart of a fourth embodiment of the verification method for the thermal balance of the nuclear power plant according to the present invention;
FIG. 8 is a schematic diagram of a historical power curve of core thermal power provided by the present invention;
FIG. 9 is a comparative verification plot;
fig. 10 is a DCS connection diagram.
Detailed Description
For a more clear understanding of the technical features, objects and effects of the present invention, embodiments of the present invention will now be described in detail with reference to the accompanying drawings.
Referring to fig. 1, a schematic structural diagram of an alternative embodiment of a nuclear power plant thermal balance verification apparatus 100 according to the present invention is shown.
As shown in fig. 1, the nuclear power plant thermal balance verification apparatus 100 includes: the system comprises a multi-path distribution module 10, a data acquisition module 20 and an operation processing verification module 30.
The multi-path distribution module 10 is connected with the transmitter 200 and used for distributing signals transmitted by the transmitter 200; the data acquisition module 20 is connected with the multi-path distribution module 10, and is configured to acquire a signal transmitted by the multi-path distribution module 10 and send the signal to the operation processing verification module 30; the operation processing and verifying module 30 is connected to the data acquisition module 20, and is configured to perform core thermal power calculation on the acquired data sent by the data acquisition module 20 to generate and display a core thermal power report.
Further, in some embodiments, the calculation processing and verification module 30 is further configured to perform an uncertainty calculation according to the collected data sent by the data collection module 20 to obtain the uncertainty.
Specifically, as shown in fig. 1, one path of the signal collected by the transmitter 200 is transmitted to the multi-path distribution module 10, and the other path is transmitted to the KME System 300(Performance Test Data Acquisition System). The transmitter 200 can be powered by a 24VDC power supply output by the KME system 300, and performs data transmission by a standard 4-20 mA current signal. The transmitter 200 is used for converting and transmitting signals of collecting devices (such as a temperature sensor, a flowmeter, etc.).
In the embodiment of the present invention, in order to ensure consistency between the detection signals of the nuclear power plant thermal balance verification apparatus 100 and the KEM system, the present invention provides a multi-path distribution module 10.
In some embodiments, the demultiplexing module 10 comprises: multichannel signal conversion resistance board. The multi-path signal conversion resistance board is shown in fig. 2.
Specifically, as shown in fig. 3, the multichannel signal conversion resistance board is connected to the transmitter 200, and is used for demultiplexing signals of the transmitter 200.
Specifically, as shown in fig. 3, the multi-path signal conversion resistor plate includes: a plurality of measurement channels, wherein each measurement channel may be connected in series with one or more high precision resistors. One end of the selected high-precision resistor is connected with the transmitter 200, the other end of the selected high-precision resistor is connected with the KME system 300, and the data acquisition module 20 calculates and obtains a current signal of the transmitter 200 by measuring the voltage at two ends of the high-precision resistor. A plurality of high-precision resistors can be connected in series between the transmitter 200 and the KME system 300 to realize distribution of multiple signals, as shown in fig. 3, 2 high-precision resistors are connected in series in one measurement channel, and an electric signal measured by the channel can be simultaneously distributed to two sets of verification systems, for example, one signal is connected to the verification device (data acquisition part and operation processing verification part (such as verification system 1 in fig. 3)) of the present invention, and the other signal is connected to other third party verification system (such as verification system 2 in fig. 3), so as to improve reliability of thermal balance measurement. Generally, a measuring channel is connected with a high-precision resistor in series and is connected with a verification device (a data acquisition part and an operation processing verification part) of the KME system to verify.
Optionally, in some embodiments, the high-precision resistor may adopt a 250 Ω platinum process resistor with a precision of 0.005%, and the high-precision comparison requirement of 0.01% required by the KME system 300 can be ensured by adopting a 250 Ω platinum process resistor with a precision of 0.005%.
In addition, in the embodiment of the invention, DIN35 standard guide rails can be adopted for installation, so that the installation in a KME acquisition cabinet is facilitated; the board card adopts a spring roll-connected terminal, so that the signal wire is conveniently connected, and meanwhile, the board card is provided with a jumper wire, so that a signal interface can be provided for a third-party verification system.
In some embodiments, the data acquisition module 20 includes: analog-to-digital converters and multiplexing cards.
Specifically, the multiplexing card is connected to the demultiplexing module 10, and is configured to collect a signal transmitted by the demultiplexing module 10; the analog-to-digital converter is connected with the multiplexing card and is used for performing analog-to-digital conversion on the signals acquired by the multiplexing card.
Optionally, in the embodiment of the present invention, the data acquisition module 20 may be implemented by using a multi-channel high-precision digital multimeter. For example, a digital multimeter model gishili 2701 may be employed. The 2701 type digital multimeter adopts 22-bit AD conversion, and the precision can reach +/-0.01% of the reading under the measuring range of 1-5 VDC. Wherein, the highest speed of the 7710 type built-in multiplex card is 500chs/s, and a single 7710 multiplex card can collect 20 analog quantity signals.
Furthermore, the multi-path signal conversion resistance plate and the data acquisition and processing part can be used as a verification tool of a heat balance system and a stability criterion tool of a heat balance test, and can also be connected into a DCS system to be used for fault diagnosis and data acquisition and analysis of the DCS card. For instruments or actuating mechanisms which need multipath collection and are abnormal in analog quantity output and input, a multipath signal conversion resistance plate can be connected in series, input and output signals are analyzed, and whether DCS card faults exist or not is positioned.
For instrument or regulating valve instruction signals with higher time sequence requirements, the multi-channel signal conversion circuit board can be simultaneously accessed into an instrument loop and a regulating valve instruction output loop, and the time sequence relation of the accessed signals can be accurately measured.
In some embodiments, the thermal equilibrium test requires the measurement of the following data: atmospheric pressure, feed water differential pressure, feed water temperature, ARE (Main feed water Flow Control System) feed water pressure value, VVP (Main Steam System) Steam pressure value, blowdown Flow rate. For a second generation unit of a certain nuclear power station, a three-loop design is adopted, the sewage discharge flow is collected into one instrument, and the signals of 14 local transmitters 200 are required to be collected in total; for a third generation unit of a nuclear power plant, a four-loop design is adopted, each steam generator is provided with a blowdown flow meter, and 21 local transmitter 200 signals are required to be collected totally. Therefore, the number of signals to be acquired is calculated according to the thermal balance test of the nuclear power unit, and 7710 board card number and acquisition scripts are selected.
Optionally, in the embodiment of the present invention, the operation processing verification module 30 is mainly developed through a programming environment and a communication protocol matched with the digital multimeter, in some embodiments, VBA macrolanguage interface programming development may be adopted, and signal routing inspection and acquisition of the 2701 type digital multimeter are realized through an RJ45 interface in a manner of dynamic link library call by using the existing operational advantages of data storage and data stream guidance of Excel software; the functions of signal engineering quantity value conversion, secondary statistical screening, thermal balance power calculation result report output consistent with KME, total uncertainty calculation, unit power trend display, result picture display and the like are realized in a macro processing mode.
Specifically, referring to fig. 4, a schematic flow chart of a first embodiment of a method for verifying a thermal balance of a nuclear power plant according to the present invention is shown.
As shown in fig. 4, in this embodiment, the method for verifying the thermal balance of the nuclear power plant includes the following steps:
step S401, the data acquisition module 20 acquires the signal transmitted by the multi-path distribution module 10, and sends the signal to the operation processing verification module 30.
In step S402, the operation processing and verifying module 30 receives the collected data sent by the data collecting module 20.
Step S403, the operation processing verification module 30 performs core thermal power calculation on the collected data to generate and display a core thermal power report.
In some embodiments, the calculation process validation module 30 performs core thermal power calculations on the collected data to generate a core thermal power report and displays the report including: the operation processing verification module 30 acquires the acquired data according to the preset acquisition time and the preset acquisition period; calculating the thermal power of the reactor core by adopting a first data processing method to obtain the thermal power of the historical reactor core; or, the second data processing method is adopted to calculate the thermal power of the reactor core, and the real-time thermal power of the reactor core and/or the historical thermal power of the reactor core are/is obtained.
Furthermore, after the real-time reactor core thermal power and/or the historical power are/is obtained, curve drawing can be carried out according to the historical reactor core to obtain a historical power curve; or drawing a curve according to the real-time reactor core thermal power to obtain a real-time power curve.
The reactor core thermal power report form according to the embodiment of the invention may include: the calculated real-time reactor core thermal power data, historical reactor core thermal power data, a real-time reactor core thermal power curve, a historical power curve, uncertainty and the like.
In some embodiments, as shown in fig. 5, the calculating the thermal power of the core by using the first data processing method, and obtaining the historical thermal power of the core includes:
step S501, obtaining historical data according to preset collection time and a preset collection period. The historical data includes m sets of collected data.
And S502, correcting the m groups of collected data to obtain m groups of corrected data.
Specifically, the correction of the m sets of collected data is performed to correct instrument calibration data. The instrument calibration data is corrected mainly to further improve the precision of the collected data and ensure the accuracy of the thermal balance verification. As shown in fig. 1, a temperature or pressure signal (a 4-20 mA standard signal is input by a non-intelligent instrument at the instrument side) is output by a measuring instrument through a manual operator at the instrument side on the spot, namely, the temperature or pressure signal is provided by a transmitter, and after analog-to-digital processing is performed through a multi-channel signal conversion resistance plate and a digital multimeter, a corresponding electric signal is received by an operation processing verification module 30.
Assuming that the original signal output by the measuring instrument is X, the operation processing verification module 30 receives the corresponding signal as Y, and the linear relationship corresponding to X-Y is obtained as follows: x is a × Y + b. Outputting multiple groups of signals X in measuring range of instrument i (in general)Selecting 0%, 10%, 25%, 50%, 75%, 90%, 100% of the meter range, and receiving multiple groups of corresponding signals Y by the operation processing verification module 30 i Plural groups of X i 、Y i Linear fitting was performed to obtain: and X is a 'X Y + b', so that the signal Y received by the operation processing verification module 30 can restore the measured value of the instrument to the maximum extent, and the measurement errors of the multi-path signal conversion resistance board, the data inspection card and the digital multimeter are eliminated. Wherein, the X-Y corresponding relation of each measuring channel can be obtained by the calibration of the method.
After the acquisition time is set, the data acquired by each measurement point is corrected by the instrument calibration function X ═ a '× Y + b' (data correction fitting formula) of the corresponding channel, so as to obtain corrected data.
And S503, performing primary screening on the m data of each signal to obtain primary screening data.
Specifically, the step of performing primary screening on m data of each signal to obtain primary screening data includes: carrying out mean processing on the m data of each signal to obtain a first mean value; performing standard deviation calculation on the m data of each signal to obtain a first standard deviation value; and removing bad values according to the first average value and the first standard deviation value to obtain primary screening data.
And step S504, carrying out secondary screening on the primary screening data to obtain secondary screening data.
Specifically, the secondary screening is performed on the primary screening data, and the obtaining of the secondary screening data includes: carrying out mean value processing on the primary screening data to obtain a second mean value; calculating the standard deviation of the primary screening data to obtain a second standard deviation value; and removing bad values according to the second average value and the second standard deviation value to obtain secondary screening data.
And step S505, judging whether the bad value rejection rate of the secondary screening data is greater than a threshold value.
And step S506, if yes, carrying out reliability analysis.
And step S507, if not, carrying out mean value processing on the secondary screening data to obtain a historical engineering measured value.
And step S508, calculating the heat balance flow according to the historical engineering measured values and by combining the instrument pipeline and the fluid characteristic parameters to obtain a historical heat balance flow value.
Specifically, the measured differential pressure value of the standard orifice plate on the water supply pipeline is obtained according to part 2 of measuring the full pipe fluid flow rate by using a differential pressure device installed in a circular section pipeline: and (3) calculating the water supply flow of each loop by using a calculation formula of the orifice plate according to the characteristic parameters of the instrument pipeline and the fluid, so as to obtain a historical heat balance flow value.
And S509, performing heat balance test calculation according to the historical heat balance flow value and by combining a calculation formula of the thermal power of the reactor core to obtain the historical thermal power of the reactor core.
Specifically, data ARE collected in a certain selected time period for at least 20 minutes to obtain m groups of data, the obtained m groups of data ARE corrected, then an arithmetic mean value X0 is obtained for m data of each signal (which refers to each of atmospheric pressure, water supply differential pressure, water supply temperature, ARE water supply pressure value, VVP steam pressure value and sewage discharge flow), a standard deviation delta 0 is calculated, then first screening is carried out, if Abs (Xj-X0) > k delta 0(k is a coverage factor for screening, k is more than 1; Abs is an absolute value), Xj is removed, and n data ARE left; and then, the arithmetic mean value of the remaining n data is calculated again, the second screening is carried out according to the standard of the first screening to eliminate bad values, and k data are remained. If the reject rate of the bad value exceeds 5 percent (threshold value), the reliability analysis of the signal point is considered to be needed; and if the bad value rejection rate of all the signals is lower than 5%, calculating the corresponding engineering measured value by using the arithmetic mean value of the k data, and then calculating the thermal power of the reactor core.
In some embodiments, as shown in FIG. 6, performing the core thermal power calculation using the second data processing method, and obtaining the real-time core thermal power and/or the historical core thermal power comprises:
step S601, acquiring real-time data according to preset acquisition time and a preset acquisition cycle.
And step S602, correcting the real-time data to obtain a real-time engineering measurement value.
It is to be understood that the modification of the real-time data in this step may employ the same modification method as that of step S502.
And step S603, calculating the heat balance flow according to the real-time engineering measured value and by combining the instrument pipeline and the fluid characteristic parameters to obtain a real-time heat balance flow value.
And S604, performing heat balance test calculation according to the real-time heat balance flow value and by combining a calculation formula of the thermal power of the reactor core to obtain the real-time thermal power of the reactor core.
Specifically, in this embodiment, after the real-time data is acquired according to the set acquisition time and the set acquisition period, the acquired real-time data is corrected to obtain a real-time engineering measurement value, a thermal balance calculation is performed based on the real-time engineering measurement value to obtain a real-time thermal balance flow value, and a thermal balance test calculation is performed according to the real-time thermal balance flow value to obtain the real-time core thermal power.
The embodiment can realize real-time calculation of the core thermal power.
In some embodiments, as shown in FIG. 7, performing the core thermal power calculation using the second data processing method, and obtaining the real-time core thermal power and/or the historical core thermal power comprises:
and S701, acquiring m groups of data according to preset acquisition time and a preset acquisition period.
And S702, correcting the m groups of data to obtain m groups of engineering measured values.
It is to be understood that the modification of the real-time data in this step may employ the same modification method as that of step S502.
And step S703, performing heat balance flow calculation according to the m groups of engineering measured values and by combining instrument pipelines and fluid characteristic parameters to obtain m groups of heat balance flow values.
And S704, performing heat balance test calculation according to the m groups of heat balance flow values and by combining a calculation formula of the core thermal power to obtain m groups of core thermal power. And the m groups of reactor core thermal power are historical reactor core thermal power.
In the embodiment of the present invention, the historical core thermal power and the real-time core thermal power may be calculated by using a core thermal power method. The following description is given only by way of a simple example.
Specifically, the calculation of the thermal power of the reactor by the thermal equilibrium method is based on the enthalpy equilibrium of the primary loop and the secondary loop of each steam generator. The enthalpy rise of the process medium in the two loops of the steam generator, namely the heat quantity transferred to the two loops by the primary loop, can be calculated by measuring the temperature, the pressure, the flow and other data of the process medium in the two loops of the steam generator, and the thermal power of the reactor can be calculated according to the principle of energy balance by comprehensively considering the energy obtained and output by the primary loop through other equipment. If the steam generator does not discharge sewage in the test process, the calculation formula of the thermal power of the reactor core is as follows:
in the above formula: w delta Pr is the thermal power, MWth, transmitted to a reactor coolant system by other heat sources except a reactor core; hv-wet steam enthalpy, kJ/kg, calculated on the basis of the outlet pressure value of each steam generator; he-feedwater enthalpy, kJ/kg, calculated according to the feedwater temperature and pressure value at the inlet of each steam generator; qe-feedwater flow (i.e., thermal equilibrium flow value), kg/s, is calculated from the differential measurement of the test orifice plate pressure and the fluid density at the upstream pressure junction.
The method comprises the steps of combining parameters such as feed water enthalpy, wet steam enthalpy and feed water density with feed water temperature, feed water pressure and steam pressure, calling a dynamic link library for calculating water and steam properties, and calculating a formula library function (adopting an IAPWS-IF97 formula) by using physical properties of water and steam.
Specifically, as shown in fig. 8, by calculating the historical core thermal power, a curve can be drawn based on the calculated historical core thermal power to obtain a historical power curve.
As can be seen from fig. 8, by performing curve drawing, the variation trend of the thermal balance power of the unit can be fed back in real time, and whether the unit has reached a stable thermal balance state or not can be timely judged and grasped based on the power curve, and whether a subsequent test can be started or not can be timely judged, so that the parameter optimization of the thermal power related function is ensured to have sufficient accuracy, and the safety risk of the subsequent transient test being out of control is reduced.
In the embodiment of the invention, the second data processing method is adopted to directly calculate the thermal power of the reactor core without screening all the collected groups of data, and the obtained thermal power value of the reactor core is displayed in a curve form, so that the power change trend can be conveniently observed, and if abnormal mutation occurs, the corresponding original data analysis reason can be searched.
The following comparison and verification are performed by using a full power thermal balance test of a unit No. 1 of a certain nuclear power station, and the result is shown in FIG. 9. At VS in fig. 9, the nuclear power plant thermal balance verification apparatus 100 according to an embodiment of the present invention is shown.
As can be seen from fig. 9, the thermal balance verification apparatus 100 of the nuclear power plant of the present invention can achieve a good verification effect, can replace the existing verification apparatus, and save a lot of cost, and has the advantages of short sampling time and high precision, and can be simultaneously accessed to multiple verification systems for calculation verification.
Further, the nuclear power plant thermal balance verification method further comprises the following steps: carrying out mean value calculation on the m groups of heat balance flow values to obtain a process quantity mean value; performing average calculation on the thermal powers of the m groups of reactor cores to obtain the average value of the thermal powers of the reactor cores; and calculating according to the average value of the thermal power of the reactor core to obtain the comprehensive uncertainty.
Specifically, the integrated uncertainty includes: class a uncertainty and class B uncertainty. The integrated uncertainty is used to perform an analysis of the measurement channel error.
Wherein, the A-type uncertainty comprises: and standard error (x) of a sample collected by each measuring channel and error (y) of a fitting formula of an instrument calibration data correction link. Wherein the class a uncertainty of each measurement channel meter is the root of the sum of the squares of x and y.
Class B uncertainties include: measuring the error of each environment of the channel, comprising: measuring errors of the sensor, the transmitter, the measuring channel and the sampling resistor. And the B-type uncertainty of each measuring channel instrument is the root of the sum of squares of the environmental errors.
For example, the acquisition time is 20 minutes, the sampling period is 0.01s (i.e., 100 points are acquired per second), and the thermal power of the core can be calculated according to the real-time data to draw a thermal power curve of the core. Alternatively, the 100 th sample data is selected as a set of calculated core thermal power (i.e., calculated once per second), and there are 1200 sets of core thermal power data. The class A uncertainty of the 1200 core thermal powers can be obtained by calculating the mean and standard deviation from the 1200 sets of core thermal power data. In addition, in the measurement process, system errors are not changed, the class B uncertainty of the measurement channel is not changed, and meanwhile, the class A uncertainty of the measurement channel can be ignored for each group of sampling points, so that the measurement uncertainty of the core thermal power can be calculated according to the class B uncertainty of each channel of each group of sampling data. The combined uncertainty of the core thermal power is then determined by the evolution of the sum of the squares of the two uncertainties (i.e., the class A uncertainty and the class B uncertainty).
Further, the present invention can also perform thermal balance error analysis. Specifically, the thermal balance error can be calculated, and the thermal balance error analysis can be performed according to the calculation result of the thermal balance error.
The thermal balance error calculation is performed by a conventional general method, and is described below by using a simple example. Specifically, the heat balance error calculation needs to decompose errors into errors of each measuring channel and an intermediate variable, and adopts a heat balance error calculation method consistent with a KME system, and relates to the calculation of relative errors of water supply temperature and water supply pressure, relative errors of steam pressure, relative errors of water supply pressure difference, relative errors of atmospheric pressure, relative errors of water supply flow, relative errors of outflow coefficients, relative errors of expansion coefficients, relative errors of pipeline inner diameters, relative errors of pore plate inner diameters, relative errors of water supply density, relative errors of SG outlet wet steam enthalpy values, relative errors of steam quality, relative errors of saturated steam enthalpy values, relative errors of saturated water enthalpy values and relative errors of main water supply enthalpy values. The relative error of the water supply temperature, the relative error of the water supply pressure, the relative error of the steam pressure, the relative error of the water supply pressure difference and the relative error of the atmospheric pressure are the errors of the measurement channel.
The invention solves the comparison and verification problem of the thermal balance test of the nuclear power plant, plays the roles of calculation and verification and replacing imported standard equipment to avoid technical support of the external party, saves a large amount of expenses, has the advantages of short sampling time and high precision, and can be simultaneously accessed into a plurality of verification systems for calculation and verification.
The thermal power trend curve of the reactor core can be used as the criterion of unit stability during the thermal balance test more intuitively, the verification precision of the thermal balance related control and protection function is improved, the stable operation time of the unit is shortened, the efficiency of the related test after the unit is critical is improved, and the risk of out-of-control transient test is reduced.
For instruments or actuating mechanisms with abnormal analog quantity output and input, a multi-channel signal conversion resistance plate can be connected in series to analyze input and output signals and position whether the DCS card has a fault or not. For instrument or regulating valve instruction signals with higher time sequence requirements, the multi-channel signal conversion circuit board can be simultaneously accessed into an instrument loop and a regulating valve instruction output loop, and the time sequence relation of the accessed signals can be accurately measured. The schematic diagram of the connection with the DCS control system is shown in fig. 10.
The method can effectively solve the verification problem of the KME system 300 heat balance algorithm in the debugging and starting process of the nuclear power plant, can accurately judge the stability of the reactor core as the criterion of the stability of the unit during the heat balance test, executes the heat balance parameter verification related test, shortens the time of stable operation of the unit, improves the efficiency of the related test after the unit is critical, and reduces the risk of out-of-control transient test. The invention is also suitable for DCS card fault diagnosis and data acquisition and analysis.
Furthermore, the invention has low cost, autonomously designs a multi-path acquisition circuit, autonomously compiles a data processing and calculating method, adopts various calculating modes, can draw a reactor core real-time thermal power curve, is convenient for analyzing and comparing the power stability trend of a unit, can monitor the thermal power of the reactor core in real time, can be used as an effective criterion for the stability of the reactor core, has the advantages of universal portable design, easy use and maintenance, transparent algorithm and data processing process and recorded intermediate calculation data and process.
The embodiments in the present description are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other. The device disclosed by the embodiment corresponds to the method disclosed by the embodiment, so that the description is simple, and the relevant points can be referred to the method part for description.
Those of skill would further appreciate that the various illustrative elements and algorithm steps described in connection with the embodiments disclosed herein may be implemented as electronic hardware, computer software, or combinations of both, and that the various illustrative components and steps have been described above generally in terms of their functionality in order to clearly illustrate this interchangeability of hardware and software. 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.
The steps of a method or algorithm described in connection with the embodiments disclosed herein may be embodied directly in hardware, in a software module executed by a processor, or in a combination of the two. A software module may reside in Random Access Memory (RAM), memory, Read Only Memory (ROM), electrically programmable ROM, electrically erasable programmable ROM, registers, hard disk, a removable disk, a CD-ROM, or any other form of storage medium known in the art.
The above embodiments are merely illustrative of the technical ideas and features of the present invention, and are intended to enable those skilled in the art to understand the contents of the present invention and implement the present invention, and not to limit the scope of the present invention. All equivalent changes and modifications made within the scope of the claims of the present invention should be covered by the claims of the present invention.
Claims (15)
1. A nuclear power plant thermal balance verification apparatus, comprising: the system comprises a multi-path distribution module, a data acquisition module and an operation processing verification module;
the multi-path distribution module is connected with the transmitter and used for distributing signals transmitted by the transmitter;
the data acquisition module is connected with the multi-path distribution module and is used for acquiring signals transmitted by the multi-path distribution module and transmitting the signals to the operation processing verification module;
the operation processing verification module is connected with the data acquisition module and is used for calculating the thermal power of the reactor core of the acquired data sent by the data acquisition module so as to generate and display a thermal power report of the reactor core.
2. The nuclear power plant thermal balance verification apparatus as claimed in claim 1, wherein the operation processing verification module is further configured to perform uncertainty calculation according to the collected data sent by the data collection module to obtain uncertainty.
3. The nuclear power plant thermal balance verification apparatus as claimed in claim 1, wherein the demultiplexing module comprises: a multi-channel signal conversion resistance plate;
the multi-channel signal conversion resistance plate is connected with the transmitter and used for carrying out multi-channel distribution on the signals transmitted by the transmitter.
4. The nuclear power plant thermal balance verification apparatus as claimed in claim 3, wherein the multiplex signal conversion resistor plate includes: a plurality of measurement channels, each of the measurement channels comprising one or more high precision resistors.
5. The nuclear power plant thermal balance verification apparatus as claimed in claim 1, wherein the data acquisition module comprises: an analog-to-digital converter and a multiplexer card;
the multiplexing card is connected with the multi-path distribution module and is used for collecting signals transmitted by the multi-path distribution module;
the analog-to-digital converter is connected with the multiplex card and is used for performing analog-to-digital conversion on signals acquired by the multiplex card.
6. A nuclear power plant thermal balance verification method is characterized by comprising the following steps:
the data acquisition module acquires signals transmitted by the multi-path distribution module and sends the signals to the operation processing verification module;
the operation processing verification module receives the acquired data sent by the data acquisition module;
and the operation processing verification module is used for calculating the thermal power of the reactor core according to the acquired data so as to generate and display a thermal power report of the reactor core.
7. The nuclear power plant thermal balance verification method as claimed in claim 6, wherein the calculating and processing verification module performs core thermal power calculation on the collected data to generate and display a core thermal power report, and the method includes:
the operation processing verification module acquires the acquired data according to preset acquisition time and a preset acquisition period;
calculating the thermal power of the reactor core by adopting a first data processing method to obtain the thermal power of the historical reactor core;
or, the second data processing method is adopted to calculate the thermal power of the reactor core, and the real-time thermal power of the reactor core and/or the historical thermal power of the reactor core are/is obtained.
8. The nuclear power plant thermal balance verification method of claim 7, further comprising:
drawing a curve according to the historical reactor core to obtain a historical power curve;
or drawing a curve according to the real-time reactor core thermal power to obtain a real-time power curve.
9. The nuclear power plant thermal balance verification method of claim 7, wherein the calculating core thermal power using the first data processing method, and obtaining historical core thermal power comprises:
acquiring historical data according to the preset acquisition time and the preset acquisition period; the historical data comprises m groups of collected data;
correcting the m groups of collected data to obtain m groups of corrected data;
screening m data of each signal once to obtain primary screening data;
performing secondary screening on the primary screening data to obtain secondary screening data;
judging whether the bad value rejection rate of the secondary screening data is greater than a threshold value;
if yes, carrying out reliability analysis;
and if not, carrying out mean value processing on the secondary screening data to obtain a historical engineering measured value.
10. The nuclear power plant thermal balance verification method according to claim 9, wherein the primary screening of the m data of each signal to obtain primary screened data comprises:
carrying out mean processing on the m data of each signal to obtain a first mean value;
calculating the standard deviation of the m data of each signal to obtain a first standard deviation value;
and removing bad values according to the first average value and the first standard deviation value to obtain the primary screening data.
11. The nuclear power plant thermal balance verification method according to claim 10, wherein the performing secondary screening on the primary screening data to obtain secondary screening data comprises:
carrying out mean value processing on the primary screening data to obtain a second mean value;
calculating the standard deviation of the primary screening data to obtain a second standard deviation value;
and removing bad values according to the second average value and the second standard deviation value to obtain the secondary screening data.
12. The nuclear power plant thermal balance verification method as claimed in claim 9, wherein the performing of the core thermal power calculation using the first data processing method to obtain the historical core thermal power further comprises:
calculating heat balance flow according to the historical engineering measured value and by combining with instrument pipelines and fluid characteristic parameters to obtain a historical heat balance flow value;
and performing heat balance test calculation according to the historical heat balance flow value and by combining a calculation formula of the core thermal power to obtain the historical core thermal power.
13. The nuclear power plant thermal balance verification method as claimed in claim 7, wherein the performing core thermal power calculations using the second data processing method to obtain real-time core thermal power and/or historical core thermal power comprises:
acquiring real-time data according to the preset acquisition time and the preset acquisition period;
correcting the real-time data to obtain a real-time engineering measurement value;
calculating the heat balance flow according to the real-time engineering measured value and by combining instrument pipelines and fluid characteristic parameters to obtain a real-time heat balance flow value;
and performing heat balance test calculation according to the real-time heat balance flow value and by combining a calculation formula of the thermal power of the reactor core to obtain the real-time thermal power of the reactor core.
14. The nuclear power plant thermal balance verification method as claimed in claim 7, wherein the performing core thermal power calculations using the second data processing method to obtain real-time core thermal power and/or historical core thermal power comprises:
acquiring m groups of data according to the preset acquisition time and the preset acquisition period;
correcting the m groups of data to obtain m groups of engineering measured values;
performing heat balance flow calculation according to the m groups of engineering measured values and by combining instrument pipelines and fluid characteristic parameters to obtain m groups of heat balance flow values;
performing heat balance test calculation according to the m groups of heat balance flow values and by combining a calculation formula of the reactor core thermal power to obtain m groups of reactor core thermal power; and the m groups of reactor core thermal power are the historical reactor core thermal power.
15. The nuclear power plant thermal balance verification method of claim 14, further comprising:
carrying out average calculation on the m groups of heat balance flow values to obtain a process quantity average value;
performing average calculation on the thermal powers of the m groups of reactor cores to obtain the average value of the thermal powers of the reactor cores;
and calculating according to the average value of the thermal power of the reactor core to obtain comprehensive uncertainty.
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