CN109192337B

CN109192337B - G of pressurized water reactor outer nuclear measuring systemkParameter checking method and device

Info

Publication number: CN109192337B
Application number: CN201810756467.7A
Authority: CN
Inventors: 郭远熊; 费瑞银; 洪志强; 郑超雄; 彭松
Original assignee: China General Nuclear Power Corp; CGN Power Co Ltd; Daya Bay Nuclear Power Operations and Management Co Ltd; Lingdong Nuclear Power Co Ltd; Lingao Nuclear Power Co Ltd
Current assignee: China General Nuclear Power Corp; CGN Power Co Ltd; Daya Bay Nuclear Power Operations and Management Co Ltd; Lingdong Nuclear Power Co Ltd; Lingao Nuclear Power Co Ltd
Priority date: 2018-07-11
Filing date: 2018-07-11
Publication date: 2020-03-03
Anticipated expiration: 2038-07-11
Also published as: CN109192337A

Abstract

The application is suitable for the field of reactor control and protection systems, and provides a G of a pressurized water reactor outer nuclear measurement system_kThe parameter checking method and device comprise the following steps: determining G according to thermal power variable of test instrument system_kParameters, determining G from ionization chamber current of RPN channel_kVerify the parameters and then pass through G_kParameter and G_kComparing the absolute value of the difference of the verification parameters with a preset threshold value to determine G_kWhether the parameters apply. By confirming G_kApplicable parameters, G guaranteed to be used for_kThe parameters are suitable for stable operation of the system, and the adjustment times are reduced.

Description

G of pressurized water reactor outer nuclear measuring systemkParameter checking method and device

Technical Field

The application belongs to the field of reactor control and protection systems, and particularly relates to a reactorG of pressurized water reactor outer nuclear measurement system_kParameter checking method, device and computer readable storage medium.

Background

The RPN system is a nuclear instrumentation system used by nuclear power plants to ensure that neutron activity is monitored persistently. The nuclear power displayed by the RPN system is an important index for the nuclear power plant operating personnel to master the safe operation of the nuclear power plant. General core power requirement uses G_kThe parameters are corrected. Any one of G_kImproper parameter settings can result in the RPN system not being able to properly display the actual nuclear power of the reactor.

The existing nuclear power plant operation technical specification requires that whether the deviation between the nuclear power provided by the power range and the core thermal power (Pth) provided by KIT (centralized data processing system) is lower than 1.5% is checked every day, and if the deviation is not lower than 1.5%, the power range Gk coefficient of the RPN system needs to be adjusted.

Disclosure of Invention

In view of the above, the embodiment of the present application provides a G of an out-of-core nuclear measurement system of a pressurized water reactor_kParameter checking method and device for solving the problem of how to confirm calculated G_kThe question of whether the parameter applies.

A first aspect of an embodiment of the present application provides a G of an out-of-core measurement system of a pressurized water reactor_kThe parameter checking method comprises the following steps:

determining G from thermal power variable of test instrument system_kA parameter;

determining G from ionization chamber current of RPN channel_kVerifying the parameters;

judging the G_kParameter and G_kVerifying whether the absolute value of the difference value of the parameters is smaller than a preset threshold value or not;

if the absolute value of the difference is smaller than a preset threshold, determining the G_kThe parameters apply.

A second aspect of an embodiment of the present application provides a G of a system for extranuclear measurement of a pressurized water reactor_kParameter verification device includes:

a parameter determination module for determining the thermal power variation of the test instrument systemQuantity determination G_kA parameter;

a verification parameter determination module for determining G from the ionization chamber current of the RPN channel_kVerifying the parameters;

a judging module for judging the G_kParameter and G_kVerifying whether the absolute value of the difference value of the parameters is smaller than a preset threshold value or not;

an application module, configured to determine the G if the absolute value of the difference is smaller than a preset threshold_kThe parameters apply.

A third aspect of embodiments of the present application provides a computer-readable storage medium storing a computer program which, when executed by a processor, implements the G of the out-of-core nuclear measurement system of a pressurized water reactor as described above_kAnd (5) a parameter checking method.

Compared with the prior art, the embodiment of the application has the advantages that: determining G according to thermal power variable of test instrument system_kParameters, determining G from ionization chamber current of RPN channel_kVerify the parameters and then pass through G_kParameter and G_kComparing the absolute value of the difference of the verification parameters with a preset threshold value to determine G_kWhether the parameters apply. By confirming G_kApplicable parameters, G guaranteed to be used for_kThe parameters are suitable for stable operation of the system, and the adjustment times are reduced.

Drawings

In order to more clearly illustrate the technical solutions in the embodiments of the present application, the drawings needed to be used in the embodiments or the prior art descriptions will be briefly described below, and it is obvious that the drawings in the following description are only some embodiments of the present application, and it is obvious for those skilled in the art to obtain other drawings based on these drawings without inventive exercise.

FIG. 1 shows a diagram G of an extra-core measurement system of a pressurized water reactor according to an embodiment of the present application_kA flow diagram of a parameter checking method;

FIG. 2 is a block diagram of a system for nuclear measurements outside a pressurized water reactor G according to an embodiment of the present application_kA detailed flowchart of step S10 in the parameter verification method;

FIG. 3 is a block diagram of an external nuclear measurement system G of a pressurized water reactor according to an embodiment of the present disclosure_kA detailed flowchart of step S20 of the parameter verification method;

FIG. 4 is a block diagram of a system for nuclear measurements outside a pressurized water reactor G according to an embodiment of the present application_kThe structure schematic diagram of the parameter checking device.

Detailed Description

In the following description, for purposes of explanation and not limitation, specific details are set forth, such as particular system structures, techniques, etc. in order to provide a thorough understanding of the embodiments of the present application. It will be apparent, however, to one skilled in the art that the present application may be practiced in other embodiments that depart from these specific details. In other instances, detailed descriptions of well-known systems, devices, circuits, and methods are omitted so as not to obscure the description of the present application with unnecessary detail.

In order to explain the technical solution described in the present application, the following description will be given by way of specific examples.

It will be understood that the terms "comprises" and/or "comprising," when used in this specification and the appended claims, specify the presence of stated features, integers, steps, operations, elements, and/or components, but do not preclude the presence or addition of one or more other features, integers, steps, operations, elements, components, and/or groups thereof.

It is also to be understood that the terminology used in the description of the present application herein is for the purpose of describing particular embodiments only and is not intended to be limiting of the application. As used in the specification of the present application and the appended claims, the singular forms "a," "an," and "the" are intended to include the plural forms as well, unless the context clearly indicates otherwise.

The first embodiment is as follows:

referring to FIG. 1, a first aspect of the present disclosure provides a system G for measuring the nuclear density of a pressurized water reactor_kThe parameter checking method comprises the following steps:

s10, according toThermal power variable determination G for a test instrument system_kAnd (4) parameters.

In this embodiment, the test instrumentation system (KME system, also referred to as a two-circuit thermal balance system) has the following functions: the instrument data acquisition function, the simulation function, the heat balance test function.

Specifically, referring to fig. 2, step S10 includes:

s11, carrying out a heat balance test of the test instrument system, and acquiring a heat power variable through the test instrument system;

s12, obtaining relative average nuclear power measured by the RPN channel;

s13, according to the thermal power variable, relative average nuclear power and G'_kParameter calculation G_kParameter, said G'_kThe parameter is G before the heat balance test_kAnd (4) parameters.

Wherein, the heat balance test in step S11 specifically includes: the method comprises the steps of measuring physical parameters such as temperature, pressure and flow of a secondary loop working medium in a steam generator, calculating enthalpy rise generated when the secondary loop working medium passes through the steam generator according to the physical parameters to obtain energy transmitted to the secondary loop by a primary loop of the reactor, calculating energy obtained and lost energy of the primary loop through other equipment, and finally calculating thermal power of a reactor core of the reactor according to an energy conservation principle, namely the thermal power variable referred by the embodiment. The thermal power variable is a linear function of the temperature difference of the primary circuit and the flow rate, which is independent of the fuel burn-up. The measurement of nuclear power is a linear function of neutron flux as a variable.

The RPN channel in step S12 is a part of the RPN system. An RPN system, namely an out-of-reactor nuclear measurement system, measures parameters such as reactor power, power change rate, radial and axial distribution of power by using a series of neutron detectors distributed outside a reactor pressure vessel, and is one of important systems directly related to reactor safety, namely nuclear power refers to the amount of energy released in a reactor in unit time. In a reactor core, the number of fissions per unit volume of time that occur is proportional to the neutron flux density at that point. Reactor power is measured by measuring the neutron flux density at a certain point. When the measuring point is far from the control rod, the local disturbance caused by moving the control rod has little influence on the measurement.

Specifically, S12 includes:

s121, acquiring the nuclear power of an RPN channel in the KDC system at multiple moments in a thermal balance time period;

and S122, calculating the average value of the nuclear power of the RPN channel at a plurality of moments, and determining the average value as the relative average nuclear power.

In this embodiment, the KDC system is a terminal display system that acquires data from the KIT system or the KIC system. The KIT system is a centralized data processing system, and the KIC system is a power station computer and a control system.

In step S121, core power variation trend tracking data of four RPN channels in the KDC system in the thermal equilibrium time period is obtained. Referring to table 1, table 1 is the nuclear power data for each RPN channel obtained for a certain thermal equilibrium test.

TABLE 1 Nuclear Power for each RPN channel when performing the thermal balance test

Time of day	RPN channel 1	RPN channel 2	RPN channel 3	RPN channel 4
					9:13	99.925	99.912	99.868	99.621
9:14	99.796	100.291	100.007	99.786
					9:15	99.605	99.771	99.815	99.422
9:16	99.649	100.062	100.255	99.358
					9:17	99.881	99.607	99.579	99.775
9:18	99.847	99.483	100.070	99.653
					9:19	99.655	99.931	99.927	99.670
9:20	99.958	100.017	100.026	99.737
					9:21	99.889	99.859	99.659	99.841
9:22	99.720	100.222	99.895	99.815
					9:23	99.952	99.832	99.977	99.641
9:24	99.676	99.485	99.601	99.565
					9:25	99.630	100.058	100.026	99.421
9:26	99.866	99.775	99.567	99.643
					9:27	99.746	99.645	99.672	99.878
9:28	99.700	99.849	99.436	99.373
					9:29	100.177	99.779	99.706	99.942
9:30	99.775	99.857	99.866	99.611
					9:31	99.508	99.887	99.531	99.790
9:32	99.523	99.815	99.634	99.838
					9:33	99.681	99.700	99.491	99.651
Average value of Pr	99.769	99.849	99.791	99.668

In step S122, the nuclear power data of each RPN channel is averaged to obtain the relative average nuclear power Pr (% FP). Wherein, the relative average nuclear power Pr of the RPN channel 1₁(% FP) 99.769; relative average nuclear power Pr of RPN channel 2₂(% FP) 99.849; relative average nuclear power Pr of RPN channel 3₃(% FP) 99.791; relative average nuclear power Pr of RPN channel 4₄(% FP) is 99.668.

Step S12 further includes:

s123, acquiring nuclear power of an RPN channel in the KIT system or the KIC system at multiple moments in a heat balance time period;

and S124, calculating the average value of the nuclear power of the RPN channel at a plurality of moments, and determining the average value as the relative average nuclear power.

In this embodiment, when the KDC system is unavailable, the KIT system or the KIT system may further obtain the core power of the RPN channel at multiple times. The execution steps of this embodiment are similar to the embodiment of calculating the relative average core power in the KDC system, and the detailed steps can be referred to this embodiment and will not be described herein again.

In step S13, G_kThe parameters can be represented by formula G_k＝G’_k×(Pth/Pr_k) And (6) calculating. Wherein, G'_kThe parameter is G before the heat balance test_kParameter, Pth thermal power variable, Pr_kReactor power (i.e., relative average nuclear power) as measured by the KME thermal balance test. k is the serial number of the RPN channel, and can take values of 1, 2, 3 and 4. Through this step, G of each RPN channel can be calculated_kParameters, but calculated G_kThe parameters are not checked and G cannot be determined_kWhether the parameters apply.

S20, determining G according to the ionization chamber current of the RPN channel_kAnd verifying the parameters.

In this step, the KIT system or the KIT system, the KDC system, and the LSS system may track the ionization chamber current value on the RPN channel. In one example, the RPN system has four measurement channels, each channel uses six short ionization chambers for measurement, which is equivalent to dividing the height of one RPN measurement channel into six sections, and each section of height can measure the current value.

Specifically, referring to fig. 3, step S20 includes:

s201, obtaining an ionization chamber current average value in an RPN channel in a KDC system, and collecting a current power conversion coefficient of the RPN system;

s202, calculating and checking relative average power according to the ionization chamber current average value and the current power conversion coefficient;

s203, determining G according to the calculated relative average power and the thermal power variable acquired by the test instrument system_kAnd verifying the parameters.

An average of ionization chamber current in each of the four channels of the RPN in the KDC system over a thermal equilibrium time period is obtained. Calculating the average value of each channel IU and IL according to each ionization chamber current, wherein IU is I1+ I2+ I3; IL is I4+ I5+ I6, and I1 to I6 represent average values of currents in the first ionization chamber to the sixth ionization chamber, respectively.

In step S201, the obtaining an ionization chamber current average value in an RPN channel in the KDC system includes:

s2011, obtaining the current of an ionization chamber in an RPN channel in the KDC system at a plurality of moments;

and S2022, calculating the current average value of the ionization chamber according to the current.

Referring to table 2, table 2 shows the current and the average current values of the ionization chamber of RPN channel 1 obtained from a certain thermal equilibrium test.

TABLE 2 Current and average Current values for ionization Chambers of RPN channel 1

And acquiring current power conversion coefficients of the RPN system, including KU and KL, which correspond to IU and IL respectively. The current power conversion coefficient can be obtained from a corresponding nuclear power unit. And if the nuclear power generating unit is a non-digital unit, acquiring a current power conversion coefficient arranged in the unit from a professional department of instruments of the nuclear power plant. For a digital unit, due to different system settings, the current-power conversion coefficient can be acquired from a field cabinet or an RPS (radiation protection system).

In step S202, the relative average power is calculated and verified according to the ionization chamber current and the current power conversion coefficient. The checking calculation of the relative average power is specifically calculated as follows: pr' (IU × KU + IL × KL) × 12.

In step S203, G is determined according to the verified relative average power and the thermal power variable obtained by the test instrument system_kAnd verifying the parameters. G_kThe calculation formula of the verification parameters is as follows: g_{k checking}＝Pth/Pr’。

Specifically, step S20 further includes:

s204, obtaining an ionization chamber current average value in an RPN channel in the KIT system or the KIC system, and collecting a current power conversion coefficient of the RPN system;

s205, calculating the relative average power of the nuclear power according to the ionization chamber current and the current power conversion coefficient;

s206, according to the relative average power of the nuclear power and the thermal power change acquired by the test instrument systemQuantity determination G_kAnd verifying the parameters.

In this embodiment, when the KDC system is not available, the ionization chamber current average in the RPN channel may also be obtained by the KIT system or the KIC system. The implementation steps of the present embodiment and the calculation of G in KDC system_kThe embodiments of the verification parameters are similar, and the detailed steps can be referred to the embodiments, which are not described herein again.

S30, judging the G_kParameter and G_kVerifying whether the absolute value of the difference value of the parameters is smaller than a preset threshold value or not;

s40, if the absolute value of the difference is smaller than a preset threshold, determining G_kThe parameters apply.

In this step, G obtained by the thermal equilibrium test_kParameters and G obtained by measuring the value of the current in the ionization chamber_kComparing the verification parameters, judging whether the absolute value of the difference between the two is less than a preset threshold value, and if so, judging that G is the absolute value_kThe parameters apply. In one example, the predetermined threshold comprises 0.0050, G measured for each RPN channel_kParameter and G_kThe verification parameters are shown in table 3.

TABLE 3G measured for each RPN channel_kParameter and G_kThe parameters and their differences are verified.

Parameter(s)	RPN channel 1	RPN channel 2	RPN channel 3	RPN channel 4
					G_k	0.9794	0.9766	0.9767	0.9797
G_{k checking}	0.9805	0.9762	0.9791	0.9799
					Difference value	-0.0011	0.0003	-0.0024	-0.0002

As can be seen from Table 3, the RPN channels 1-4 calculate G_kParameter and G_kThe absolute values of the differences between the verification parameters are all less than the preset threshold of 0.0050, and thus, G for the four RPN channels_kThe parameters are applicable.

Optionally, the conditions for performing the thermal balance test of the test instrument system include:

the nuclear island and the conventional island are in a stable working condition for at least 2 hours;

grid frequency: f is more than or equal to 49.8 and less than or equal to 50.2;

the water level of the steam generator is stable and is in an automatic adjusting state, and the change of the water level in a narrow-range instrument is not more than 5%;

the water supply flow of the steam generator is stable;

the pressure and the water level of the pressure stabilizer are stable and are in an automatic control mode;

the nuclear power is higher than the thermal power of the reactor core, the peak value of the nuclear power does not exceed the preset control limit value, the reduction of the load and dilution of the two loops is completed within the designated time before the test, and the continuous overheating of the reactor core is controlled to approach and not exceed 0.3 ℃;

the absolute value of the difference between the average temperature of the reactor coolant and the reference temperature is less than 0.5 ℃;

the blowdown flow of the blowdown system of the steam generator is stable;

the RPN system, the KIT system, the KME system, the KDC system and the LSS system are in an available state.

In the present embodiment, the nuclear island is a general term for a nuclear reactor in a containment of the nuclear power plant and various systems related to the reactor. The primary function of the nuclear island is to generate steam using nuclear fission energy. The nuclear island plant mainly comprises a reactor plant (containment), a nuclear fuel plant, a nuclear auxiliary plant, a nuclear service plant, an exhaust chimney, an electrical plant, an emergency diesel generator plant and the like. The conventional island is a general name of a turbo generator unit in a nuclear power device, supporting facilities thereof and a plant where the turbo generator unit and the supporting facilities are located. The main function of the conventional island is to convert the heat energy of the steam generated by the nuclear island into the mechanical energy of a steam turbine, and then the mechanical energy is converted into electric energy through a generator. The conventional island plant mainly comprises a steam turbine plant, a cooling water pump room, a water treatment plant room, a transformer area structure, a switching station, a network control building, a transformer substation, a power distribution station and the like. The nuclear island and the conventional island are in a stable working condition, which means that the running conditions of the nuclear island and the conventional island normally run according to a set value, and no abnormal condition occurs.

The frequency of the nuclear power unit is controlled as follows: f is more than or equal to 49.8 and less than or equal to 50.2.

The steam generator is the boundary of a primary loop and a secondary loop of the nuclear power plant, and steam generated by the steam generator is dried by the primary steam-water separator and the secondary steam-water separator and then pushes a steam turbine generator to generate electricity. In order to ensure that the data of the heat balance measurement is stable, the water level of the steam generator is kept stable and is in an automatic adjusting state, the change of the water level in a narrow-range instrument is not more than 5%, and the water supply flow of the steam generator is stable; the pressure and the water level of the pressure stabilizer are stable and are in an automatic control mode; the blowdown flow of the blowdown system of the steam generator is stable.

The nuclear power of the reactor core is larger than the thermal power of the reactor core, the peak value of the nuclear power does not exceed the preset control limit value, and meanwhile, the load and dilution of the two loops are finished within the specified time before the test, so that the continuous overheating of the reactor core is controlled to approach and not exceed the specified temperature value. Here, the specified time includes 10 minutes, and the specified temperature value is higher than the temperature reference value by 0.3 ℃. The temperature reference value refers to the rated temperature of the core operation, and the designated temperature value is slightly higher than the temperature reference value.

The absolute value of the difference between the average reactor coolant temperature and the reference temperature is less than 0.5 ℃. The reference temperature herein refers to the nominal temperature at which the reactor coolant is operating normally.

When the heat balance test is performed, the RPN system, KIT system, KME system, KDC system, LSS system (LOCA monitoring system) are also required to be in a usable state.

It should be understood that, the sequence numbers of the steps in the foregoing embodiments do not imply an execution sequence, and the execution sequence of each process should be determined by its function and inherent logic, and should not constitute any limitation to the implementation process of the embodiments of the present application.

Example two:

referring to FIG. 2, a second aspect of the present disclosure provides a system G for measuring the nuclear density of a pressurized water reactor_kParameter verification device includes:

a parameter determination module 10 for determining G according to the thermal power variable of the test instrument system_kA parameter;

a verification parameter determination module 20 for determining G from the ionization chamber current of the RPN channel_kVerifying the parameters;

a judging module 30 for judging the G_kParameter and G_kVerifying whether the absolute value of the difference value of the parameters is smaller than a preset threshold value or not;

an applicable module 40, configured to determine the G if the absolute value of the difference is smaller than a preset threshold_kThe parameters apply.

Optionally, the parameter determining module 10 includes:

the thermal power acquisition unit is used for carrying out a thermal balance test of the test instrument system and acquiring a thermal power variable through the test instrument system;

a relative average nuclear power obtaining unit, configured to obtain a relative average nuclear power measured by the RPN channel;

G_ka parameter calculation unit for calculating a parameter based on the measured valuesVariable of thermal power, relative average nuclear power and G'_kParameter calculation G_kParameter, said G'_kThe parameter is G before the heat balance test_kAnd (4) parameters.

Optionally, the relative average nuclear power obtaining unit includes:

the first acquisition unit is used for acquiring the nuclear power of an RPN channel in the KDC system at multiple moments in a thermal balance time period;

and the first calculation unit is used for calculating the average value of the nuclear power of the RPN channel at a plurality of moments and determining the average value as the relative average nuclear power.

Optionally, the relative average nuclear power obtaining unit includes:

the second acquisition unit is used for acquiring the nuclear power of the KIT system or the RPN channel in the KIC system at multiple moments in a thermal balance time period;

and the second calculation unit is used for calculating the average value of the nuclear power of the RPN channel at a plurality of moments and determining the average value as the relative average nuclear power.

Optionally, the verification parameter determining module 20 includes:

the first parameter acquisition module is used for acquiring the current average value of an ionization chamber in an RPN channel in the KDC system and acquiring the current power conversion coefficient of the RPN system;

the first relative average power calculation module is used for calculating the relative average power of the nuclear power according to the ionization chamber current and the current power conversion coefficient;

first G_kA verification parameter module for determining G according to the relative average power of the nuclear power and the thermal power variable obtained by the test instrument system_kAnd verifying the parameters.

Optionally, the first parameter obtaining module includes:

the current acquisition unit is used for acquiring the current of an ionization chamber in an RPN channel in the KDC system at a plurality of moments;

and the current calculating unit is used for calculating the current average value of the ionization chamber according to the current.

Optionally, the verification parameter determining module 20 further includes:

the second parameter acquisition module is used for acquiring the current average value of an ionization chamber in an RPN channel in the KIT system or the KIC system and acquiring the current power conversion coefficient of the RPN system;

the second relative average power calculation module is used for calculating the relative average power of the nuclear power according to the ionization chamber current and the current power conversion coefficient;

second G_kA verification parameter module for determining G according to the relative average power of the nuclear power and the thermal power variable obtained by the test instrument system_kAnd verifying the parameters.

Optionally, the implementation conditions of the thermal power obtaining unit include:

grid frequency: f is more than or equal to 49.8 and less than or equal to 50.2;

the water supply flow of the steam generator is stable;

the nuclear power is higher than the thermal power of the reactor core, the peak value of the nuclear power does not exceed a preset control limit value, and meanwhile, the reduction of the load and dilution of the two loops is completed within a specified time before the test, so that the continuous overheating of the reactor core is controlled to approach and not exceed a specified temperature value;

the blowdown flow of the blowdown system of the steam generator is stable;

Example three:

In the above embodiments, the descriptions of the respective embodiments have respective emphasis, and reference may be made to the related descriptions of other embodiments for parts that are not described or illustrated in a certain embodiment.

The above-mentioned embodiments are only used for illustrating the technical solutions of the present application, and not for limiting the same; although the present application has been described in detail with reference to the foregoing embodiments, it should be understood by those of ordinary skill in the art that: the technical solutions described in the foregoing embodiments may still be modified, or some technical features may be equivalently replaced; such modifications and substitutions do not substantially depart from the spirit and scope of the embodiments of the present application and are intended to be included within the scope of the present application.

Claims

1. G of pressurized water reactor out-of-core measurement system_kThe parameter checking method is characterized by comprising the following steps:

if the absolute value of the difference is smaller than a preset threshold, determining the G_kThe parameters are applicable;

determining G according to thermal power variable of test instrument system_kThe parameters include:

carrying out a thermal balance test of a test instrument system, and acquiring a thermal power variable through the test instrument system;

obtaining relative average nuclear power measured by an RPN channel;

according to the thermal power variable, relative average nuclear power and G'_kParameter calculation G_kParameter, said G'_kThe parameter is G before the heat balance test_kA parameter;

the conditions for carrying out the thermal balance test of the test instrument system comprise:

the nuclear power is higher than the thermal power of the reactor core, the peak value of the nuclear power does not exceed the preset control limit value, the two-loop load reduction and dilution are completed within the specified time before the test, and the continuous overheating of the reactor core is controlled to approach and not exceed the specified temperature value.

2. The system of claim 1, wherein the system comprises a pressurized water reactor, an extranuclear measurement system, and a nuclear measurement system_kThe parameter verification method is characterized in that the obtaining of the relative average nuclear power measured by the RPN channel comprises the following steps:

acquiring the nuclear power of an RPN channel in a KDC system at multiple moments in a thermal balance time period;

and calculating the average value of the nuclear power of the RPN channel at a plurality of moments, and determining the average value as the relative average nuclear power.

3. The system of claim 1, wherein the system comprises a pressurized water reactor, an extranuclear measurement system, and a nuclear measurement system_kThe parameter verification method is characterized in that the obtaining of the relative average nuclear power measured by the RPN channel comprises the following steps:

acquiring nuclear power of a KIT system or RPN channels in the KIC system at multiple moments in a thermal balance time period;

4. The system of claim 2, wherein the system comprises a pressurized water reactor external nuclear measurement system G_kMethod for checking parameters, characterized in that said determination G of the ionization chamber current according to the RPN channel is carried out_kValidating parameters, including:

acquiring the current average value of an ionization chamber in an RPN channel in a KDC system, and acquiring the current power conversion coefficient of the RPN system;

calculating the relative average power of the nuclear power according to the ionization chamber current and the current power conversion coefficient;

determining G according to the relative average power of the nuclear power and the thermal power variable acquired by the test instrument system_kValidating parameters。

5. The system of claim 4, wherein the system comprises a pressurized water reactor_kThe parameter verification method is characterized in that the obtaining of the ionization chamber current average value in the RPN channel in the KDC system comprises the following steps:

obtaining the current of an ionization chamber in an RPN channel in a KDC system at a plurality of moments;

and calculating the average value of the current of the ionization chamber according to the current.

6. The system of claim 3, wherein the system comprises a pressurized water reactor_kMethod for checking parameters, characterized in that said determination G of the ionization chamber current according to the RPN channel is carried out_kValidating parameters, including:

acquiring the current average value of an ionization chamber in an RPN channel in a KIT system or a KIC system, and acquiring the current power conversion coefficient of the RPN system;

determining G according to the relative average power of the nuclear power and the thermal power variable acquired by the test instrument system_kAnd verifying the parameters.

7. The system of claim 1, wherein the system comprises a pressurized water reactor, an extranuclear measurement system, and a nuclear measurement system_kThe parameter calibration method is characterized in that the condition for carrying out the thermal balance test of the test instrument system further comprises the following steps:

grid frequency: f is more than or equal to 49.8 and less than or equal to 50.2;

the water supply flow of the steam generator is stable;

the blowdown flow of the blowdown system of the steam generator is stable;

8. G of pressurized water reactor out-of-core measurement system_kParameter verification device, its characterized in that includes:

a parameter determination module for determining G according to the thermal power variable of the test instrument system_kA parameter;

an application module, configured to determine the G if the absolute value of the difference is smaller than a preset threshold_kThe parameters are applicable;

the parameter determination module comprises:

G_ka parameter calculation unit for calculating the thermal power according to the thermal power variable, the relative average nuclear power and G'_kParameter calculation G_kParameter, said G'_kThe parameter is G before the heat balance test_kA parameter;

the implementation conditions of the thermal power acquisition unit include:

9. The system of claim 8, wherein the system comprises a pressurized water reactor outside-core measurement system G_kThe parameter verifying apparatus is characterized in that the relative average nuclear power obtaining unit includes:

10. The system of claim 8, wherein the system comprises a pressurized water reactor outside-core measurement system G_kThe parameter verifying apparatus is characterized in that the relative average nuclear power obtaining unit includes:

11. The system of claim 9, wherein the system comprises a pressurized water reactor external nuclear measurement system G_kThe parameter verification device is characterized in that the verification parameter determination module comprises:

12. The system of claim 11, wherein the system comprises a pressurized water reactor outside-core measurement system G_kThe parameter calibration device is characterized in that the first parameter obtaining module comprises:

13. The system of claim 10, wherein the system comprises a pressurized water reactor external nuclear measurement system G_kThe parameter verification device is characterized in that the verification parameter determination module comprises:

14. The system of claim 8, wherein the system comprises a pressurized water reactor outside-core measurement system G_kThe parameter calibration device is characterized in that the implementation conditions of the thermal power acquisition unit further include:

grid frequency: f is more than or equal to 49.8 and less than or equal to 50.2;

the water supply flow of the steam generator is stable;

the blowdown flow of the blowdown system of the steam generator is stable;

15. A computer-readable storage medium, in which a computer program is stored, which, when being executed by a processor, implements the G of the system for ex-core nuclear measurement of a pressurized water reactor according to any one of claims 1 to 7_kAnd (5) a parameter checking method.