CN112259271A - Reactor core thermal power calculation method and device for nuclear power station DCS - Google Patents
Reactor core thermal power calculation method and device for nuclear power station DCS Download PDFInfo
- Publication number
- CN112259271A CN112259271A CN202011038968.5A CN202011038968A CN112259271A CN 112259271 A CN112259271 A CN 112259271A CN 202011038968 A CN202011038968 A CN 202011038968A CN 112259271 A CN112259271 A CN 112259271A
- Authority
- CN
- China
- Prior art keywords
- enthalpy
- result data
- data
- operation result
- calculation
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
- G21D3/002—Core design; core simulations; core optimisation
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
Abstract
A thermal power calculation method and device for a nuclear power station DCS comprise the following steps: and acquiring core monitoring data in a preset time period, wherein the monitoring data comprises pressure data of the core and temperature data of the core. And acquiring intermediate operation result data according to the reactor core monitoring data, wherein the intermediate operation result data comprise enthalpy operation result data and are acquired by performing enthalpy operation on the reactor core monitoring data. And resetting the enthalpy coefficient of the enthalpy operation according to the obtained enthalpy operation result data. And acquiring the thermal power of the reactor core according to the intermediate operation result data. Because the enthalpy coefficient of the enthalpy operation is set according to the enthalpy operation result data in the intermediate operation result data, the directional and quantitative setting of the enthalpy coefficient in the enthalpy operation is realized, and the thermal power calculation of the nuclear power station DCS is faster and more accurate.
Description
Technical Field
The invention relates to the technical field of signal processing of a nuclear power station control system, in particular to a method and a device for calculating thermal power of a reactor core of a nuclear power station DCS.
Background
A Distributed Control System (DCS) is a new computer Control System, which is developed and evolved based on a centralized Control System, and is referred to as a Distributed Control System. The DCS is a multi-stage computer system composed of a process control stage and a process monitoring stage and using a communication network as a link, integrates 4C technologies such as computer, communication, display, and control, and has the basic ideas of decentralized control, centralized operation, hierarchical management, flexible configuration, and convenient configuration. At present, a distributed control system is generally used in a nuclear power plant to realize control of the nuclear power plant, because a DCS (distributed control system) bears most control functions of the whole plant, configuration data of the whole DCS is huge, the DCS can be comprehensively tested before leaving a factory, but process parameters in the control system still need to be optimized or changed and adjusted during field debugging and unit operation, and the execution frequency of process parameter optimization during debugging and operation of the power plant is very high. The optimization of the technological parameters for calculating the reactor core power of the nuclear power station is the core work of setting the technological parameters of a nuclear power plant control system during debugging and running of the power plant, and is that the nuclear power plant control system monitors a reactor, a primary loop and a secondary loop and then carries out enthalpy operation on monitoring data to obtain the reactor core power of the nuclear power station. When the DCS system of the nuclear power station at the present stage calculates the reactor core power, along with the penetration of the unit burnup or the abnormal occurrence of the thermal power, the formula coefficients for calculating the reactor core power cannot be directionally and quantitatively set.
Disclosure of Invention
The technical problem that in the prior art, the calculation parameter setting of the nuclear power station DCS system cannot be directionally and quantitatively set during core thermal power calculation is solved.
According to a first aspect, an embodiment provides a core thermal power calculation method for a nuclear power plant DCS, comprising:
acquiring reactor core monitoring data in a preset time period; the core monitoring data comprises pressure data of the core and temperature data of the core;
acquiring intermediate operation result data according to the reactor core monitoring data;
and acquiring the thermal power of the reactor core according to the intermediate operation result data.
Wherein, the intermediate operation result data include enthalpy operation result data, the intermediate operation result data are obtained according to the reactor core monitoring data, and the method includes:
carrying out enthalpy operation on the reactor core monitoring data to obtain enthalpy operation result data;
and resetting the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data.
In an embodiment, the resetting the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data includes:
sequentially replacing enthalpy coefficients in the preset time period according to a preset sequence and a preset interval time;
acquiring enthalpy operation result data in the preset time period;
and acquiring an enthalpy coefficient corresponding to the enthalpy operation result data in a preset interval range in the preset time period, and setting the enthalpy coefficient as the enthalpy coefficient of the enthalpy operation.
In an embodiment, the resetting the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data further includes:
and displaying the enthalpy operation result data in the preset time period in a form and/or a graph.
In one embodiment, the obtaining of the intermediate operation result data according to the core monitoring data further includes:
density calculation result data obtained by performing density calculation on the reactor core monitoring data and the enthalpy calculation result data;
and resetting the density calculation coefficient of the density calculation according to the density calculation result data.
In one embodiment, the resetting the density calculation coefficient according to the density calculation result data includes:
sequentially replacing density operation coefficients in the preset time period according to a preset sequence and a preset interval time;
acquiring density operation result data in the preset time period;
and acquiring a density operation coefficient corresponding to the density operation result data in a preset interval range in the preset time period, and setting the density operation coefficient as the density operation coefficient of the density operation.
In one embodiment, the resetting the density calculation coefficient of the density calculation according to the density calculation result data further includes:
and displaying the density operation result data in the preset time period by using a table and/or a graph.
In one embodiment, the core pressure data includes a primary heat pipe section pressure.
In one embodiment, the core temperature data includes a primary cold leg temperature and a primary hot leg temperature.
According to a second aspect, an embodiment provides a computer readable storage medium comprising a program executable by a processor to implement the method according to the first aspect.
According to a third aspect, an embodiment provides a core thermal power calculation apparatus for a nuclear power plant DCS, comprising:
the monitoring data acquisition module is used for acquiring reactor core monitoring data in a preset time period; the core monitoring data comprises pressure data of the core and temperature data of the core;
the thermal power calculation module is used for acquiring intermediate operation result data according to the reactor core monitoring data; the intermediate operation result data comprise enthalpy operation result data, and the thermal power calculation module is further used for carrying out enthalpy operation on the reactor core monitoring data to obtain the enthalpy operation result data and resetting an enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data;
and the thermal power logic calculation module is used for acquiring the thermal power of the reactor core according to the intermediate operation result data.
According to the thermal power calculation method and the thermal power calculation device for the nuclear power station DCS in the embodiment, firstly, reactor core monitoring data in a preset time period are obtained, wherein the monitoring data comprise reactor core pressure data and reactor core temperature data; and then acquiring intermediate operation result data according to the reactor core monitoring data, wherein the intermediate operation result data comprise enthalpy operation result data and are acquired by performing enthalpy operation on the reactor core monitoring data. And resetting the enthalpy coefficient of the enthalpy operation according to the obtained enthalpy operation result data. And acquiring the thermal power of the reactor core according to the intermediate operation result data. Because the enthalpy coefficient of the enthalpy operation is set according to the enthalpy operation result data in the intermediate operation result data, the directional and quantitative setting of the enthalpy coefficient in the enthalpy operation is realized, and the thermal power calculation of the nuclear power station DCS is faster and more accurate.
Drawings
FIG. 1 is a schematic diagram of a two-loop heat balance scheme in one embodiment;
FIG. 2 is a parametric illustration of core thermal power in one embodiment;
FIG. 3 is a core thermal power calculation apparatus for a nuclear power plant DCS according to an embodiment;
FIG. 4 is a block diagram of a thermal power calculation module according to an embodiment;
FIG. 5 is a schematic flow chart illustrating a method for calculating core thermal power for a nuclear power plant DCS according to an embodiment;
FIG. 6 is a diagram illustrating enthalpy operation result data according to an embodiment.
Detailed Description
The present invention will be described in further detail with reference to the following detailed description and accompanying drawings. Wherein like elements in different embodiments are numbered with like associated elements. In the following description, numerous details are set forth in order to provide a better understanding of the present application. However, those skilled in the art will readily recognize that some of the features may be omitted or replaced with other elements, materials, methods in different instances. In some instances, certain operations related to the present application have not been shown or described in detail in order to avoid obscuring the core of the present application from excessive description, and it is not necessary for those skilled in the art to describe these operations in detail, so that they may be fully understood from the description in the specification and the general knowledge in the art.
Furthermore, the features, operations, or characteristics described in the specification may be combined in any suitable manner to form various embodiments. Also, the various steps or actions in the method descriptions may be transposed or transposed in order, as will be apparent to one of ordinary skill in the art. Thus, the various sequences in the specification and drawings are for the purpose of describing certain embodiments only and are not intended to imply a required sequence unless otherwise indicated where such sequence must be followed.
The numbering of the components as such, e.g., "first", "second", etc., is used herein only to distinguish the objects as described, and does not have any sequential or technical meaning. The term "connected" and "coupled" when used in this application, unless otherwise indicated, includes both direct and indirect connections (couplings).
The nuclear power station DCS system is huge, and according to the system resource allocation state, the current security level DCS system only selects a part of signals for recording and displaying for the strategy of intermediate process signals, and the strategy is used for displaying master control room panel information and enabling maintenance personnel to retrieve necessary data information for event overview. The selected safety level DCS input and output and signal data of partial intermediate process are transmitted, stored and displayed through a special network, but for complete event process investigation, all intermediate process signals are required to carry out event restoration. For example, in the thermal power calculation of the reactor, the pressure and the temperature of the two-loop cold/heat pipe section are adopted to calculate the enthalpy entropy, and the three-loop operation signals are superposed to finally calculate the thermal power corresponding to the current reactor core. Because each nuclear power station has differences, when technological parameters for calculating the reactor core power of the nuclear power station are optimized, the technological parameters such as enthalpy and density need to be calculated according to theory, and the experience of other nuclear power station reactors cannot be directly used for reference, so the technological parameters need to be adjusted. The core thermal power calculation process of the DCS is described below by taking the method for calculating the thermal power of the two-loop core as an example.
Referring to fig. 1, a schematic diagram of a principle of two-loop thermal balance in an embodiment includes a steam generator 1 and a differential pressure transmitter 2, the steam generator 1 is provided with a main steam outlet, the differential pressure transmitter 2 is provided with a main water supply inlet, a sewage drain, a primary loop coolant inlet and a primary loop coolant outlet, the main steam outlet of the differential pressure transmitter 2 is provided with an outlet pressure transmitter 3, and the main water supply inlet of the differential pressure transmitter 2 is provided with an inlet temperature and pressure transmitter 4, an inlet differential pressure transmitter 5 and an inlet pressure transmitter 6.
Referring to fig. 2, the parameters of the core thermal power in an embodiment include a main water supply pressure 11, a main power supply temperature 12, a water supply differential pressure 13, a main steam pressure 14, a pipe valve caliber 15, a water discharge flow 16, an uncertainty calculation 17 of an uncertain link, and other heat source input thermal power 18. The main water supply pressure 11 refers to a pressure value of a main water supply inlet of the differential pressure transmitter 2, the main power supply temperature 12 refers to a temperature value of the main water supply inlet of the differential pressure transmitter 2, the water supply differential pressure 13 refers to a pressure difference value of the differential pressure transmitter 2, the main steam pressure 14 refers to a pressure value of a main steam outlet of the steam generator 1, the pipe valve caliber 15 refers to technological parameters of the steam generator 1 and the differential pressure transmitter 2, orifice diameter of an orifice plate, a ratio of the inner diameter of the orifice plate to the inner diameter of a pipeline, the inner diameter of a pressure taking flange at the upstream of the orifice plate and the like, the drainage flow 16 refers to a flow value of a sewage discharge outlet of the differential pressure transmitter 2, uncertainty calculation 17 of an uncertain link refers to uncertainty calculation caused by links of a measuring instrument, a collecting plate, a calculation formula and the like, and thermal energy brought. The DCS of the nuclear power station obtains the main water supply pressure, the main water supply temperature and the measured value of the main water supply flow differential pressure of a main water supply flow control system (ARE), the measured value of the steam pressure of a main steam system (VVP) and the blowdown steam generatorThe flow measurement value of the sewage discharge water of the system (APG) calculates the enthalpy rise generated by transferring the heat of a primary coolant medium to a secondary coolant system through a Steam Generator (SG), calculates the thermal power of the primary coolant system, and then reduces the thermal power input to the primary coolant system from other heat sources outside the reactor core to obtain the reactor core thermal power. Wherein, the heat power W of the steam generatorSGThe calculation formula is as follows:
WSG＝(HV-He)Qe-(HV-HP)QP，
wherein HVIs the enthalpy of wet steam, HeIs the main enthalpy of feed water, HPFor discharge enthalpy, QeIs the main water supply flow, QPFor blowdown flow, a measure of blowdown water flow through a steam generator blowdown system (APG).
As shown in fig. 2, the core thermal power calculation process includes a first-stage calculation layer, a second-stage calculation layer and a result calculation layer. The first-stage calculation layer comprises a feed water enthalpy calculation layer 21, a main feed water density calculation layer 22, a main feed water dynamic viscosity calculation layer 23, a saturation temperature calculation layer 25, a saturation steam enthalpy calculation layer 26 and a saturation water enthalpy calculation layer 27, the first-stage intermediate calculation results used for reactor core thermal power calculation are obtained through direct operation according to monitored original data, the second-stage calculation layer comprises a flow coefficient calculation layer 24, a wet steam enthalpy calculation layer 28, a blowdown enthalpy calculation layer 29 and a feed water flow calculation layer 31, the second-stage intermediate calculation results used for reactor core thermal power calculation are obtained through re-operation according to the first-stage intermediate calculation results, and the result calculation layer comprises a steam generator thermal power layer 32 and a reactor core thermal power layer 33 and is used for obtaining the results of reactor core thermal power calculation. Wherein, enthalpy parameters need to be set when enthalpy calculation is involved in the first-stage calculation layer, the second-stage calculation layer and the result calculation layer. Along with the deepening of the unit combustion consumption or the abnormal occurrence of the thermal power, the enthalpy parameter needs to be adjusted during the thermal power calculation. E.g. HVThe wet steam enthalpy, which is calculated by the formula:
HV＝x H″+(1-x)H＇，
wherein HVIs the wet steam enthalpy, H 'is the saturated steam enthalpy, H' is the saturated water enthalpy, x is the steam quality, isIn an important technical index of a steam generator system of a nuclear power station, in one embodiment, x refers to the dryness of steam, and the value range of x is 0.95-1. The calculation formula of H' saturated steam enthalpy is:
wherein, pi ═ Pvvp/p*,τ＝T*/t,p*＝1MPa,T*＝540K,R＝0.461526kJkg-1K-1,PvvpA saturated pressure value, a pressure value measured by a pressure sensor of the main steam system (VVP), t a saturated temperature value, kJkg-1K-1Is a unit dimension. In addition, enthalpy parameters i, J in the formulao iAnd no iThe settings of (a) are shown in the following table:
enthalpy parameters i, J in the formulai、IiAnd niThe settings of (a) are shown in the following table:
in the prior art, the heat power W of a steam generator is involvedSGThe settings for calculating the enthalpy-related parameters need to be selected on the basis of historical or empirical data. However, in the initial stage of operation of the nuclear power plant, it is necessary to select and verify the operation one by trying to accumulate historical data or empirical data. In the process of calculating the thermal power of the reactor core, the setting of enthalpy parameters is various, so a parameter setting method for calculating the thermal power of the reactor core is needed to improve the setting speed of the enthalpy parameters. The intermediate process signals of part of important logics of the current DCS have the problems of no record and no display, have no influence on the normal operation of a nuclear power plant and the monitoring of the system state, but have great significance on fault diagnosis, so a method needs to be designed, and the method can be used for carrying out fault diagnosis on the DCSAnd recording and displaying all intermediate process signals in the system according to requirements.
In the embodiment of the application, the method and the device for calculating the thermal power of the reactor core of the nuclear power station DCS are disclosed, and the enthalpy coefficient of the enthalpy operation is set according to the enthalpy operation result data in the intermediate operation result data, so that the directed and quantitative setting of the enthalpy coefficient in the enthalpy operation is realized, and the thermal power calculation of the nuclear power station DCS is faster and more accurate.
Example one
Referring to fig. 3, an embodiment of a core thermal power calculation apparatus for a nuclear power plant DCS includes a monitoring signal acquiring device 30, a thermal power calculation module 40, and a thermal power logic calculation module 50. The monitoring data acquisition module 30 is configured to acquire reactor core monitoring data in a preset time period, where the reactor core monitoring data includes reactor core pressure data and reactor core temperature data. The thermal power calculation module 40 is configured to obtain intermediate operation result data according to the reactor core monitoring data, where the intermediate operation result data includes enthalpy operation result data, and the thermal power calculation module 40 is further configured to perform enthalpy operation on the reactor core monitoring data to obtain the enthalpy operation result data, and reset an enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data. The thermal power logic calculation module 50 is configured to obtain the thermal power of the reactor core according to the intermediate operation result data. In one embodiment, the monitoring signal acquisition device 30 includes a circuit cold leg temperature acquisition module 31, a circuit hot leg pressure acquisition module 32, and a circuit hot leg temperature acquisition module 33.
Referring to fig. 4, which is a schematic diagram of a thermal power calculating module in an embodiment, the thermal power calculating module 40 includes a cold pipe section temperature enthalpy calculating module 41, a hot pipe section temperature enthalpy calculating module 42, a cold pipe section density calculating module 43, a hot pipe section density calculating module 44, an inlet energy calculating module 45, an energy conversion ratio calculating module 46, and an outlet energy calculating module 47. The cold pipe section temperature and enthalpy calculation module 41 performs enthalpy calculation on the temperature value of the primary circuit cold pipe section and the pressure value of the primary circuit hot pipe section acquired by the monitoring signal acquisition device to acquire enthalpy calculation result data (i) of the primary circuit cold pipe section. The heat pipe section temperature and enthalpy calculation module 42 performs enthalpy calculation on the temperature value of the loop heat pipe section and the pressure value of the loop heat pipe section acquired by the monitoring signal acquisition device to acquire enthalpy calculation result data of the loop heat pipe section. The cold pipe section density calculation module 43 performs density calculation on the pressure value of the hot pipe section of the primary circuit and the enthalpy calculation result data of the cold pipe section of the primary circuit to obtain density calculation result data (II) of the cold pipe section of the primary circuit. The heat pipe section density calculation module 44 performs density calculation on the pressure value of the loop heat pipe section and the enthalpy calculation result data of the loop heat pipe section to obtain density calculation result data of the loop heat pipe section. The inlet energy calculation module 45 obtains an inlet energy calculation value according to the density calculation result data of the cold pipe section of the primary circuit, outputs the inlet energy calculation value to the thermal power logic calculation module 50, and sets inlet energy calculation parameters of the inlet energy calculation module 45 through the thermal power logic calculation module 50. The outlet energy calculation module 45 obtains an outlet energy calculation value according to the density calculation result data of the loop heat pipe section, outputs the outlet energy calculation value to the thermal power logic calculation module 50, and sets outlet energy calculation parameters of the outlet energy calculation module 45 by the thermal power logic calculation module 50. The energy conversion rate calculation module 46 obtains the energy conversion rate according to the density calculation result data of the loop cold pipe section and the density calculation result data of the loop hot pipe section, and outputs the energy conversion rate to the thermal power logic calculation module 50, and the thermal power logic calculation module 50 sets the energy conversion rate calculation parameters of the energy conversion rate calculation module 46.
Referring to fig. 5, a schematic flow chart of a method for calculating core thermal power for a nuclear power plant DCS in an embodiment includes:
step one, reactor core monitoring data are obtained. Reactor core monitoring data in a preset time period are acquired, the reactor core monitoring data can be acquired in real time, historical reactor core monitoring data which can be stored can be read, and continuous reactor core monitoring data on a preferred time axis are acquired. The core monitoring data includes core pressure data and core temperature data. In one embodiment, the core pressure data includes a loop hot leg pressure and the core temperature data includes a loop cold leg temperature and a loop hot leg temperature. In one embodiment, the pressure data of the core includes the principal feedwater pressure, the feedwater differential pressure, and the principal steam pressure of the two circuits, and the temperature data of the core includes the principal feedwater temperature of the two circuits.
And step two, acquiring intermediate operation result data. The intermediate operation result data include enthalpy operation result data, and the intermediate operation result data are acquired according to the reactor core monitoring data, and include:
and carrying out enthalpy operation on the reactor core monitoring data to obtain enthalpy operation result data, and resetting an enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data.
In one embodiment, the resetting the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data includes:
sequentially replacing the enthalpy coefficients according to a preset sequence and a preset interval time in a preset time period, acquiring enthalpy operation result data in the preset time period, acquiring the corresponding enthalpy coefficients of the enthalpy operation result data in a preset interval range in the preset time period, and setting the enthalpy coefficients as the enthalpy coefficients of the enthalpy operation. In one embodiment, the enthalpy operation result data in the preset time period is displayed in a table and a graph. Referring to fig. 6, a schematic diagram of enthalpy operation result data is shown in an embodiment, where an abscissa is a time axis, an ordinate is a value of an enthalpy coefficient, different enthalpy coefficients are sequentially set in order, and obtained enthalpy operation result data corresponding to enthalpy operation are also different. The enthalpy coefficients can be sequentially replaced in a preset time period according to a preset sequence and a preset interval time, and different enthalpy coefficients can also be sequentially set. The following table is an example enthalpy coefficient table:
| serial number | Coefficient of enthalpy calculation | Coefficient value of |
| 1 | HFT001-MA1 | -27.0535 |
| 2 | HFT001-MA2 | -1.90E-01 |
| 3 | HFT001-MA3 | 4.03382 |
| 4 | HFT001-MA4 | 1.80E-03 |
| 5 | HFT001-MA5 | -18476.5 |
| 6 | HFT001-MA6 | 73.9694 |
| 7 | HFT001-MA7 | -31012.1 |
| 8 | HFT001-MA8 | 100.888 |
| 9 | HFT001-MA9 | 42.778 |
| 10 | HFT001-MA10 | 398.889 |
Respectively obtaining enthalpy operation result data of different enthalpy coefficients, and setting the corresponding enthalpy coefficient as the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data in a preset interval range.
In one embodiment, the intermediate operation result data further includes density operation result data, and the obtaining of the intermediate operation result data according to the core monitoring data includes:
and performing density calculation on the reactor core monitoring data and the enthalpy calculation result data to obtain density calculation result data, and resetting a density calculation coefficient of the density calculation according to the density calculation result data. Wherein, resetting the density calculation coefficient of the density calculation according to the density calculation result data comprises:
sequentially replacing the density operation coefficients according to a preset sequence and a preset interval time in a preset time period, acquiring density operation result data in the preset time period, acquiring the density operation coefficient corresponding to the density operation result data in the preset time period within a preset interval range, and setting the density operation coefficient as the density operation coefficient of the density operation.
The following table is an example of a density calculation coefficient table:
| serial number | Coefficient of density operation | Coefficient value of |
| 1 | RHF001-MD1 | -6.07E+11 |
| 2 | RHF001-MD2 | -9.98E+08 |
| 3 | RHF001-MD3 | -1.79E+05 |
| 4 | RHF001-MD4 | 6.90E+09 |
| 5 | RHF001-MD5 | 2.58E+06 |
| 6 | RHF001-MD6 | -7.80E+06 |
| 7 | RHF001-MD7 | -1859.18 |
| 8 | RHF001-MD8 | 2987.19 |
| 9 | RHF001-MD9 | 0.449458 |
| 10 | RHF001-MD10 | -0.371964 |
| 11 | RHF001-MD11 | 2384.15 |
| 12 | RHF001-MD12 | 1977.1 |
| 13 | RHF001- |
1000 |
The density calculation result data obtained in the preset time period is displayed in a form and a graph as the determination of the enthalpy coefficient, so that the selection and the judgment are facilitated.
In the embodiment of the application, firstly, core monitoring data in a preset time period is obtained, wherein the monitoring data comprises pressure data of a core and temperature data of the core; and then acquiring intermediate operation result data according to the reactor core monitoring data, wherein the intermediate operation result data comprise enthalpy operation result data and are acquired by performing enthalpy operation on the reactor core monitoring data. And resetting the enthalpy coefficient of the enthalpy operation according to the obtained enthalpy operation result data. And acquiring the thermal power of the reactor core according to the intermediate operation result data. Because the enthalpy coefficient of the enthalpy operation is set according to the enthalpy operation result data in the intermediate operation result data, the directional and quantitative setting of the enthalpy coefficient in the enthalpy operation is realized, and the thermal power calculation of the nuclear power station DCS is faster and more accurate.
As shown in fig. 4, in the prior art, the thermal power calculation module lacks historical record data of an intermediate process for the enthalpy calculation result data of the loop cold pipe section (i), the enthalpy calculation result data of the loop hot pipe section (iii), the density calculation result data of the loop cold pipe section (ii), and the density calculation result data of the loop hot pipe section (iv), so that the thermal power calculation module is similar to a black box and cannot perform parameter analysis and adjustment. When the core thermal power calculation device in the DCS system calculates the core thermal power, along with the deepening of the unit combustion consumption, when the thermal power is abnormal, the influence of the logic calculation abnormality and each input cannot be diagnosed due to the lack of intermediate process data. In the embodiment of the application, the monitoring and recording of the intermediate signal of the thermal power calculation module can be realized through the software tool disclosed by the application, and a data file can be generated. The data can be integrated into a simulation platform to carry out parameter fine adjustment and setting, verify and optimize an enthalpy operation and density calculation algorithm, and finally a black box of a thermal power calculation module in a reactor core thermal power calculation device is changed into a white box.
Those skilled in the art will appreciate that all or part of the functions of the various methods in the above embodiments may be implemented by hardware, or may be implemented by computer programs. When all or part of the functions of the above embodiments are implemented by a computer program, the program may be stored in a computer-readable storage medium, and the storage medium may include: a read only memory, a random access memory, a magnetic disk, an optical disk, a hard disk, etc., and the program is executed by a computer to realize the above functions. For example, the program may be stored in a memory of the device, and when the program in the memory is executed by the processor, all or part of the functions described above may be implemented. In addition, when all or part of the functions in the above embodiments are implemented by a computer program, the program may be stored in a storage medium such as a server, another computer, a magnetic disk, an optical disk, a flash disk, or a removable hard disk, and may be downloaded or copied to a memory of a local device, or may be version-updated in a system of the local device, and when the program in the memory is executed by a processor, all or part of the functions in the above embodiments may be implemented.
The present invention has been described in terms of specific examples, which are provided to aid understanding of the invention and are not intended to be limiting. For a person skilled in the art to which the invention pertains, several simple deductions, modifications or substitutions may be made according to the idea of the invention.
Claims (10)
1. A core thermal power calculation method for a nuclear power station DCS is characterized by comprising the following steps:
acquiring reactor core monitoring data in a preset time period; the core monitoring data comprises pressure data of the core and temperature data of the core;
acquiring intermediate operation result data according to the reactor core monitoring data;
acquiring the thermal power of the reactor core according to the intermediate operation result data;
wherein, the intermediate operation result data include enthalpy operation result data, the intermediate operation result data are obtained according to the reactor core monitoring data, and the method includes:
carrying out enthalpy operation on the reactor core monitoring data to obtain enthalpy operation result data;
and resetting the enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data.
2. The method of claim 1, wherein said resetting the enthalpy coefficient of the enthalpy operation based on the enthalpy operation result data comprises:
sequentially replacing enthalpy coefficients in the preset time period according to a preset sequence and a preset interval time;
acquiring enthalpy operation result data in the preset time period;
and acquiring an enthalpy coefficient corresponding to the enthalpy operation result data in a preset interval range in the preset time period, and setting the enthalpy coefficient as the enthalpy coefficient of the enthalpy operation.
3. The method of claim 2, wherein said resetting the enthalpy coefficient of the enthalpy operation based on the enthalpy operation result data further comprises:
and displaying the enthalpy operation result data in the preset time period in a form and/or a graph.
4. The method of claim 1, wherein the intermediate operational result data further comprises density operational result data, and the obtaining intermediate operational result data from the core monitoring data comprises:
density calculation result data obtained by performing density calculation on the reactor core monitoring data and the enthalpy calculation result data;
and resetting the density calculation coefficient of the density calculation according to the density calculation result data.
5. The method of claim 4, wherein said resetting the density calculation coefficients of the density calculation based on the density calculation result data comprises:
sequentially replacing density operation coefficients in the preset time period according to a preset sequence and a preset interval time;
acquiring density operation result data in the preset time period;
and acquiring a density operation coefficient corresponding to the density operation result data in a preset interval range in the preset time period, and setting the density operation coefficient as the density operation coefficient of the density operation.
6. The method of claim 5, wherein resetting density calculation coefficients for the density calculation based on the density calculation result data further comprises:
and displaying the density operation result data in the preset time period by using a table and/or a graph.
7. The method of claim 4 wherein the core pressure data includes a primary heat pipe section pressure.
8. The method of claim 7 wherein the core temperature data includes a primary cold leg temperature and a primary hot leg temperature.
9. A computer-readable storage medium, characterized by comprising a program executable by a processor to implement the method of any one of claims 1-8.
10. A core thermal power calculation device for a nuclear power plant DCS, comprising:
the monitoring data acquisition module is used for acquiring reactor core monitoring data in a preset time period; the core monitoring data comprises pressure data of the core and temperature data of the core;
the thermal power calculation module is used for acquiring intermediate operation result data according to the reactor core monitoring data; the intermediate operation result data comprise enthalpy operation result data, and the thermal power calculation module is further used for carrying out enthalpy operation on the reactor core monitoring data to obtain the enthalpy operation result data and resetting an enthalpy coefficient of the enthalpy operation according to the enthalpy operation result data;
and the thermal power logic calculation module is used for acquiring the thermal power of the reactor core according to the intermediate operation result data.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011038968.5A CN112259271B (en) | 2020-09-28 | 2020-09-28 | Reactor core thermal power calculation method and device for nuclear power station DCS |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202011038968.5A CN112259271B (en) | 2020-09-28 | 2020-09-28 | Reactor core thermal power calculation method and device for nuclear power station DCS |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN112259271A true CN112259271A (en) | 2021-01-22 |
| CN112259271B CN112259271B (en) | 2023-09-12 |
Family
ID=74234588
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202011038968.5A Active CN112259271B (en) | 2020-09-28 | 2020-09-28 | Reactor core thermal power calculation method and device for nuclear power station DCS |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN112259271B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113871037A (en) * | 2021-09-14 | 2021-12-31 | 中广核研究院有限公司 | Reactor operation control method, reactor operation control device, computer equipment and storage medium |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4145922A (en) * | 1976-12-06 | 1979-03-27 | Westinghouse Electric Corp. | Thermal power measurement apparatus |
| US4654186A (en) * | 1983-03-11 | 1987-03-31 | Framatome & Cie. | Device for determination of the power of a pressurized water nuclear reactor |
| CN1274162A (en) * | 2000-06-21 | 2000-11-22 | 北京和利时系统工程股份有限公司 | Method for measuring power of pressurized-water reactor core for nuclear power station |
| US20100272223A1 (en) * | 2006-02-28 | 2010-10-28 | Atsushi Fushimi | Nuclear reactor system and nuclear reactor control method |
| CN104200061A (en) * | 2014-07-31 | 2014-12-10 | 北京广利核系统工程有限公司 | Method for calculating power of third-generation nuclear power station pressurized water reactor core |
-
2020
- 2020-09-28 CN CN202011038968.5A patent/CN112259271B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4145922A (en) * | 1976-12-06 | 1979-03-27 | Westinghouse Electric Corp. | Thermal power measurement apparatus |
| US4654186A (en) * | 1983-03-11 | 1987-03-31 | Framatome & Cie. | Device for determination of the power of a pressurized water nuclear reactor |
| CN1274162A (en) * | 2000-06-21 | 2000-11-22 | 北京和利时系统工程股份有限公司 | Method for measuring power of pressurized-water reactor core for nuclear power station |
| US20100272223A1 (en) * | 2006-02-28 | 2010-10-28 | Atsushi Fushimi | Nuclear reactor system and nuclear reactor control method |
| CN104200061A (en) * | 2014-07-31 | 2014-12-10 | 北京广利核系统工程有限公司 | Method for calculating power of third-generation nuclear power station pressurized water reactor core |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113871037A (en) * | 2021-09-14 | 2021-12-31 | 中广核研究院有限公司 | Reactor operation control method, reactor operation control device, computer equipment and storage medium |
Also Published As
| Publication number | Publication date |
|---|---|
| CN112259271B (en) | 2023-09-12 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Hashemian | On-line monitoring applications in nuclear power plants | |
| CN106128529B (en) | A kind of On-line Measuring Method of reactor core three-dimensional power distribution | |
| Buchberger et al. | Leak estimation in water distribution systems by statistical analysis of flow readings | |
| CN108758357B (en) | A kind of localization of bursted pipe method based on the analysis of water supply network change value of pressure | |
| CN105895175B (en) | A kind of method for demarcating nuclear reactor exit thermocouple | |
| CN112259271B (en) | Reactor core thermal power calculation method and device for nuclear power station DCS | |
| De Keizer et al. | Simulation-based long-term fault detection for solar thermal systems | |
| CN107895194B (en) | Fault diagnosis method for main coolant system of nuclear power plant | |
| CN106092351A (en) | nuclear power station pipeline inner wall temperature measuring method and device | |
| Rüger et al. | Online leakage attribution to exclusion areas prototype application | |
| Zio et al. | Bootstrap and order statistics for quantifying thermal-hydraulic code uncertainties in the estimation of safety margins | |
| Coble et al. | Adaptive monitoring, fault detection and diagnostics, and prognostics system for the IRIS nuclear plant | |
| CN115016409A (en) | Nuclear power station thermal balance verification device and method | |
| CN110688152A (en) | Software reliability quantitative evaluation method combining software development quality information | |
| Cadini et al. | A model based on bootstrapped neural networks for computing the maximum fuel cladding temperature in an Rmbk-1500 nuclear reactor accident | |
| Juarsa et al. | The effect of power and cooler flow on time responds of flow stability in natural circulation phenomenon using FASSIP-01 loop | |
| Zhang et al. | Development of online validation and monitoring system for the thermal performance of nuclear power plant in service | |
| Stachura et al. | Planning of a water distribution network sensors location for a leakage isolation. | |
| Zhang et al. | Investigation of condensation process at COSMEA test facility with ATHLET code | |
| Webb et al. | Comparison of CECOR algorithm to Lagrange multiplier method to estimate reactor power distributions | |
| Karim et al. | Preliminary study on fault detection using artificial neural network for water-cooled reactors | |
| Maccari et al. | Design of a Prototypical Mock-Up for the Experimental Investigation of WCLL First-Wall Performances. Energies 2023, 16, 1685 | |
| Hashemian | Integrated online condition monitoring system for nuclear power plants | |
| Shi et al. | The Research of Function Reliability in Passive System Based on Fuzzy Theory | |
| Hastuti et al. | Thermal-hydraulic benchmarking of RSG-GAS research reactor using RELAP5 |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |