CN109192337A - The G of pressurized water reactor out-pile nuclear measurement systemkParameter verification method and device - Google Patents
The G of pressurized water reactor out-pile nuclear measurement systemkParameter verification method and device Download PDFInfo
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- CN109192337A CN109192337A CN201810756467.7A CN201810756467A CN109192337A CN 109192337 A CN109192337 A CN 109192337A CN 201810756467 A CN201810756467 A CN 201810756467A CN 109192337 A CN109192337 A CN 109192337A
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Abstract
The application is suitable for reactor Control and protection system field, provides the G of pressurized water reactor out-pile nuclear measurement systemkParameter verification method and device, comprising: the application determines G according to the thermal power variable of test-meter systemkParameter determines G according to the ionisation chamber electric current in the channel RPNkThen certificate parameter passes through GkParameter and GkThe absolute value of the difference of certificate parameter determines G compared with preset thresholdkWhether parameter is applicable in.By confirming GkParameter is applicable in, it is ensured that the G being used forkParameter applicable system stable operation reduces adjustment number.
Description
Technical field
The application belongs to reactor Control and protection system field more particularly to a kind of pressurized water reactor heap outer core measurement system
The G of systemkParameter verification method, apparatus and computer readable storage medium.
Background technique
RPN system is that nuclear power station is used to ensure that middle subactivity obtains the Nuclear Instrument system of durability monitoring.RPN system is shown
Core power be NPP Operations Personnel hold npp safety operation an important indicator.Usual core power is needed using Gk
Parameter corrects.Any one GkThe improper practical core power that can all cause RPN system that can not correctly show reactor of parameter setting.
Existing nuclear power station running technology code requirement checks core power and KIT (concentration number that power range provides daily
According to processing system) whether the deviation between the core thermal power (Pth) that provides be lower than 1.5%, if being not less than 1.5%, need
Adjust the power range Gk coefficient of RPN system.
Summary of the invention
In view of this, the embodiment of the present application provides the G of pressurized water reactor out-pile nuclear measurement systemkParameter verification method and
Device, to solve how to confirm calculated GkThe problem whether parameter is applicable in.
The first aspect of the embodiment of the present application provides a kind of G of pressurized water reactor out-pile nuclear measurement systemkParameter verification
Method, comprising:
G is determined according to the thermal power variable of test-meter systemkParameter；
G is determined according to the ionisation chamber electric current in the channel RPNkCertificate parameter；
Judge the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than preset threshold；
If the absolute value of the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
The second aspect of the embodiment of the present application provides a kind of G of pressurized water reactor out-pile nuclear measurement systemkParameter verification
Device, comprising:
Parameter determination module, for determining G according to the thermal power variable of test-meter systemkParameter；
Certificate parameter determining module, for determining G according to the ionisation chamber electric current in the channel RPNkCertificate parameter；
Judgment module, for judging the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than preset threshold；
Suitable modules, if the absolute value for the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
The third aspect of the embodiment of the present application provides a kind of computer readable storage medium, the computer-readable storage
Media storage has computer program, realizes that above-mentioned pressurized water reactor heap outer core such as is surveyed when the computer program is executed by processor
The G of amount systemkThe step of parameter verification method.
Existing beneficial effect is the embodiment of the present application compared with prior art: the application is according to the heat of test-meter system
Power and variable determines GkParameter determines G according to the ionisation chamber electric current in the channel RPNkThen certificate parameter passes through GkParameter and GkIt tests
The absolute value of the difference of parameter is demonstrate,proved compared with preset threshold, determines GkWhether parameter is applicable in.By confirming GkParameter is applicable in, can
To guarantee the G being used forkParameter applicable system stable operation reduces adjustment number.
Detailed description of the invention
It in order to more clearly explain the technical solutions in the embodiments of the present application, below will be to embodiment or description of the prior art
Needed in attached drawing be briefly described, it should be apparent that, the accompanying drawings in the following description is only some of the application
Embodiment for those of ordinary skill in the art without any creative labor, can also be according to these
Attached drawing obtains other attached drawings.
Fig. 1 is the G of pressurized water reactor out-pile nuclear measurement system provided by the embodiments of the present applicationkThe process of parameter verification method
Schematic diagram；
Fig. 2 is the G of pressurized water reactor out-pile nuclear measurement system provided by the embodiments of the present applicationkStep in parameter verification method
The idiographic flow schematic diagram of S10；
Fig. 3 is the G of pressurized water reactor out-pile nuclear measurement system provided by the embodiments of the present applicationkThe step of parameter verification method
The idiographic flow schematic diagram of S20；
Fig. 4 is the G of pressurized water reactor out-pile nuclear measurement system provided by the embodiments of the present applicationkThe structure of parameter calibrator
Schematic diagram.
Specific embodiment
In being described below, for illustration and not for limitation, the tool of such as particular system structure, technology etc is proposed
Body details, so as to provide a thorough understanding of the present application embodiment.However, it will be clear to one skilled in the art that there is no these specific
The application also may be implemented in the other embodiments of details.In other situations, it omits to well-known system, device, electricity
The detailed description of road and method, so as not to obscure the description of the present application with unnecessary details.
In order to illustrate technical solution described herein, the following is a description of specific embodiments.
It should be appreciated that ought use in this specification and in the appended claims, term " includes " instruction is described special
Sign, entirety, step, operation, the presence of element and/or component, but be not precluded one or more of the other feature, entirety, step,
Operation, the presence or addition of element, component and/or its set.
It is also understood that mesh of the term used in this present specification merely for the sake of description specific embodiment
And be not intended to limit the application.As present specification and it is used in the attached claims, unless on
Other situations are hereafter clearly indicated, otherwise " one " of singular, "one" and "the" are intended to include plural form.
Embodiment one:
Please refer to Fig. 1, the first aspect of the embodiment of the present application provides a kind of pressurized water reactor out-pile nuclear measurement system
GkParameter verification method, comprising:
S10, G is determined according to the thermal power variable of test-meter systemkParameter.
In the present embodiment, test-meter system (KME system, alternatively referred to as secondary circuit heat balance system) has following function
Can: instrumented data acquires function, analog functuion, heat balance test function.
Specifically, referring to Fig. 2, step S10 includes:
S11, the test of test-meter system heat balance is carried out, thermal power variable is obtained by test-meter system；
S12, the opposite average core power for obtaining RPN channel measurement；
S13, according to the thermal power variable, opposite average core power and G 'kParameter calculates GkParameter, the G 'kParameter
For the G before heat balance testkParameter.
Wherein, the heat balance test in step S11 specifically includes: the temperature of secondary circuit working media in measurement steam generator
The physical parameters such as degree, pressure, flow calculate secondary circuit working media by production when steam generator according to above-mentioned physical parameter
Then raw enthalpy liter calculates primary Ioops and is obtained by other equipment to obtain the energy that reactor-loop is transmitted to secondary circuit
Energy and the energy that loses, reactor core thermal power is finally calculated according to conservation of energy principle, i.e. the present embodiment is signified
Thermal power variable.Thermal power variable is the linear function of the primary Ioops temperature difference and flow velocity unrelated with burnup.The measurement of core power
Value is the linear function using neutron flux as variable.
The channel RPN in step S12 is a part of RPN system.RPN system, i.e. out-pile nuclear measurement system are with distribution
Reactor capability, power variation rate and the radial direction of power are measured in a series of neutron detectors outside reactor pressure vessel
It is to be directly related to one of important system of reactor safety core power to refer in heap in the unit time with the axially parameters such as distribution
The number to release energy.In reactor core, the fission number occurred in the unit volume unit time is proportional to the neutron of the point
Flux density.Reactor capability is measured by measuring the netron-flux density of certain point.When measuring point farther out from control rod when, move
Influence of the local dip to measurement caused by dynamic control rod is smaller.
Specifically, S12 includes:
The core power at the channel RPN multiple moment in KDC system in S121, acquisition heat balance time section；
The average value of S122, the core power at the calculating channel RPN multiple moment, are determined as the phase for the average value
To average core power.
In the present embodiment, KDC system is that the terminal display system of data is obtained from KIT system or KIC system.KIT system
For integrated data processing system, KIC system is power station computer and control system.
In step S121, obtain heat balance time section in KDC system in tetra- channels RPN core changed power trend with
Track data.Referring to table 1, table 1 is the core power data in each channel RPN that certain heat balance test obtains.
When table 1 carries out heat balance test, the core power in each channel RPN
| Time | The channel RPN 1 | The channel RPN 2 | The channel RPN 3 | The channel RPN 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 |
| Pr average value | 99.769 | 99.849 | 99.791 | 99.668 |
It in step S122, averages to the core power data in each channel RPN, obtains opposite average core power P r (%
FP).Wherein, the opposite average core power P r in the channel RPN 11(%FP) is 99.769；The opposite average core power P r in the channel RPN 22
(%FP) is 99.849；The opposite average core power P r in the channel RPN 33(%FP) is 99.791；The opposite average core in the channel RPN 4
Power P r4(%FP) is 99.668.
Step S12 further include:
The core power at the channel RPN multiple moment in KIT system or KIC system in S123, acquisition heat balance time section；
The average value of S124, the core power at the calculating channel RPN multiple moment, are determined as the phase for the average value
To average core power.
In the present embodiment, when KDC system is unavailable, it is multiple also the channel RPN can be obtained by KIT system or KIC system
The core power at moment.The execution step of the present embodiment and the embodiment that relatively flat equal core power is calculated in KDC system are similar, in detail
Thin step can be found in the embodiment, and details are not described herein.
In step S13, GkParameter can pass through formula Gk=G 'k×(Pth/Prk) calculate acquisition.Wherein, G 'kParameter is that heat is flat
G before weighing apparatus testkParameter, Pth are thermal power variable, PrkIt is (i.e. relatively flat for reactor capability measured by KME heat balance test
Equal core power).K is the serial number in the channel RPN, such as can value 1,2,3,4.By this step, the G in each channel RPN can be calculatedk
Parameter, but the G calculatedkParameter by checking computations, can not determine the GkWhether parameter is applicable in.
S20, G is determined according to the ionisation chamber electric current in the channel RPNkCertificate parameter.
In this step, the ionisation chamber electric current on the channel RPN is can be traced in KIT system or KIC system, KDC system, LSS system
Value.In one example, altogether there are four Measurement channel, each channel is measured using six short ionisation chamber, is equivalent to one RPN system
It is divided into six sections in the height of a RPN Measurement channel, every section height can measure current value.
Specifically, referring to Fig. 3, step S20 includes:
Ionisation chamber current average in S201, acquisition KDC system in the channel RPN, the current power of acquisition RPN system turn
Change coefficient；
S202, the opposite mean power of checking computations is calculated according to the ionisation chamber current average and current power conversion coefficient；
S203, G is determined according to the thermal power variable for checking opposite mean power and obtaining by test-meter systemk
Certificate parameter.
The ionisation chamber electric current obtained in every channel in the KDC system in heat balance time section in tetra- channels RPN is flat
Mean value.Each channel IU, the average value of IL, wherein IU=I1+I2+I3 are calculated according to each ionisation chamber electric current；IL=I4+I5+
I6, I1~I6 respectively represent the first ionisation chamber to the current average of the 6th ionisation chamber.
In step s 201, the ionisation chamber current average obtained in KDC system in the channel RPN, comprising:
Electric current of the ionisation chamber at multiple moment in the channel RPN in S2011, acquisition KDC system；
S2022, ionisation chamber current average is calculated according to the electric current.
Referring to table 2, table 2 is the electric current and current average of the ionisation chamber in the channel RPN 1 that certain heat balance test obtains.
The electric current and current average of the ionisation chamber in the channel table 2RPN 1
The current power conversion coefficient of RPN system, including KU, KL are acquired, it is corresponding with IU, IL respectively.Current power conversion
Coefficient can be obtained from corresponding nuclear power unit.If nuclear power unit is non-digitalization unit, obtained from instrument specialized department of nuclear power plant
Take the current power conversion coefficient being set in unit.For digitlization unit, due to the difference of each system setting, electric current function
Rate conversion coefficient can be acquired from the cabinet at scene, can also the acquisition from RPS system (radiation protecting systems).
In step S202, is calculated according to ionisation chamber electric current and current power conversion coefficient and check opposite mean power.Checking computations
Opposite mean power specifically calculates as follows: Pr '=(IU*KU+IL*KL) * 12.
In step S203, determined according to the opposite mean power of checking computations and by the thermal power variable that test-meter system obtains
GkCertificate parameter.GkThe calculation formula of certificate parameter are as follows: GK checking computations=Pth/Pr '.
Specifically, step S20 further include:
Ionisation chamber current average in S204, acquisition KIT system or KIC system in the channel RPN, acquisition RPN system
Current power conversion coefficient；
S205, the opposite mean power that core power is calculated according to the ionisation chamber electric current and current power conversion coefficient；
S206, the thermal power variable obtained according to the opposite mean power of the core power and by test-meter system are true
Determine GkCertificate parameter.
In the present embodiment, when KDC system is unavailable, it can also be obtained in the channel RPN by KIT system or KIC system
Ionisation chamber current average.The execution step of the present embodiment and G is calculated in KDC systemkThe embodiment of certificate parameter is similar, in detail
Thin step can be found in the embodiment, and details are not described herein.
S30, judge the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than preset threshold；
If the absolute value of S40, the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
In this step, the G that will be obtained by heat balance testkParameter and the G obtained by measurement ionisation chamber current valuekIt tests
Card parameter is compared, and judges whether the absolute value of difference between the two is less than preset threshold, if illustrating the GkParameter is applicable in.
In one example, preset threshold includes 0.0050, the G that each channel RPN measureskParameter and GkCertificate parameter is as shown in table 3.
The G that each channel RPN of table 3 measureskParameter and GkCertificate parameter and its difference.
| Parameter | The channel RPN 1 | The channel RPN 2 | The channel RPN 3 | The channel RPN 4 |
| Gk | 0.9794 | 0.9766 | 0.9767 | 0.9797 |
| GK checking computations | 0.9805 | 0.9762 | 0.9791 | 0.9799 |
| Difference | -0.0011 | 0.0003 | -0.0024 | -0.0002 |
As seen from Table 3, the channel RPN 1-4 calculates GkParameter and GkThe absolute value of difference between certificate parameter is small
In preset threshold 0.0050, thus, the G in this four channels RPNkParameter is applicable.
Optionally, the condition for carrying out the test of test-meter system heat balance includes:
Nuclear island and conventional island are in steady working condition at least 2 hours；
Mains frequency: 49.8≤F≤50.2；
Steam generator water level is stablized, and automatic adjustment state is in, and water level is no more than 5% in the variation of narrow range instrument；
Steam generator feedwater flow is stablized；
Voltage-stablizer pressure and stable level, and it is in automatic control mode；
Core power is higher than core thermal power, and the not super default control limit value of core power peak, while testing preceding specified time
Interior completion reduces secondary circuit load and dilution, and control reactor core persistently overheats approach and do not surpass 0.3 DEG C；
Reactor coolant mean temperature and reference temperature difference absolute value are less than 0.5 DEG C；
Steam generator blowdown system blowdown flow is stablized；
RPN system, KIT system, KME system, KDC system, LSS system are in available mode.
In the present embodiment, nuclear island is the system of the nuclear reactor and each system related with reactor in nuclear power plant containment shell
Claim.The major function of nuclear island is to generate steam using nuclear fission energy.Nuclear island factory building mainly includes reactor building (containment), core
Fuel plant, nuclear auxiliary building, core service workshop, exhaust chimney, electrical building and emergency diesel dynamo workshop etc..Conventional island
It is the general designation of Turbo-generator Set and its auxiliary facility and workshop where them in nuclear power apparatus.The major function of conventional island be by
The thermal energy for the steam that nuclear island generates is converted into the mechanical energy of steam turbine, then is transformed into electric energy by generator.Conventional island workshop master
Will include steam turbine workshop, cooling water pump house and water treatment building, transformer area structures, switchyard, network control building, substation and
Distribution substation etc..Nuclear island and conventional island are in steady working condition and refer to that the operation conditions of nuclear island and conventional island is normally transported according to setting value
Make, does not occur abnormal conditions.
The control of nuclear power unit frequency exists: 49.8≤F≤50.2.
Steam generator is the boundary of nuclear power plant's primary Ioops, secondary circuit, and the steam generated is through I and II steam-water separator
Steam turbine generator power generation is pushed after drying.In order to guarantee the data stabilization of thermal balance measurement, the water level of steam generator keeps steady
It is fixed, it is in automatic adjustment state, water level is no more than 5% in the variation of narrow range instrument, and steam generator feedwater flow is stablized；Surely
Depressor pressure and stable level, and it is in automatic control mode；Steam generator blowdown system blowdown flow is stablized.
Heap core power refers to greater than core thermal power, and the not super default control limit value of core power peak, while referring to before testing
Interior completion of fixing time reduces secondary circuit load and dilution, and control reactor core persistently overheats approach and not super assigned temperature value.Here,
Specified time includes 10 minutes, and assigned temperature value is higher than 0.3 DEG C of temperature reference value.Temperature reference value refers to the volume of reactor core operation
Determine temperature, assigned temperature value is slightly above temperature reference value.
Reactor coolant mean temperature and reference temperature difference absolute value are less than 0.5 DEG C.Reference temperature herein refers to
The rated temperature that reactor coolant works normally.
When carrying out heat balance test, RPN system, KIT system, KME system, KDC system, LSS system (LOCA prison are also required
Examining system) it is in available mode.
It should be understood that the size of the serial number of each step is not meant that the order of the execution order in above-described embodiment, each process
Execution sequence should be determined by its function and internal logic, the implementation process without coping with the embodiment of the present application constitutes any limit
It is fixed.
Embodiment two:
Referring to figure 2., the second aspect of the embodiment of the present application provides a kind of pressurized water reactor out-pile nuclear measurement system
GkParameter calibrator, comprising:
Parameter determination module 10, for determining G according to the thermal power variable of test-meter systemkParameter；
Certificate parameter determining module 20, for determining G according to the ionisation chamber electric current in the channel RPNkCertificate parameter；
Judgment module 30, for judging the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than default threshold
Value；
Suitable modules 40, if the absolute value for the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
Optionally, parameter determination module 10 includes:
Thermal power acquiring unit obtains heat by test-meter system for carrying out test-meter system heat balance test
Power and variable；
Opposite average core power obtaining unit, for obtaining the opposite average core power of RPN channel measurement；
GkParameter calculation unit, for according to the thermal power variable, opposite average core power and G 'kParameter calculates Gk
Parameter, the G 'kParameter is the G before heat balance testkParameter.
Optionally, the opposite average core power obtaining unit includes:
First acquisition unit, for obtaining the core function at the channel RPN multiple moment in the KDC system in heat balance time section
Rate；
First computing unit, the average value of the core power for calculating the channel RPN multiple moment, by the average value
It is determined as the opposite average core power.
Optionally, the opposite average core power obtaining unit includes:
Second acquisition unit, for when obtaining that the channel RPN is multiple in KIT system or KIC system in heat balance time section
The core power at quarter；
Second computing unit, the average value of the core power for calculating the channel RPN multiple moment, by the average value
It is determined as the opposite average core power.
Optionally, certificate parameter determining module 20 includes:
First parameter acquisition module acquires RPN for obtaining the ionisation chamber current average in KDC system in the channel RPN
The current power conversion coefficient of system；
First is averaged power computation module relatively, for being calculated according to the ionisation chamber electric current and current power conversion coefficient
The opposite mean power of core power；
First GkCertificate parameter module, for according to the opposite mean power of the core power and passing through test-meter system
The thermal power variable of acquisition determines GkCertificate parameter.
Optionally, first parameter acquisition module, comprising:
Electric current acquiring unit, for obtaining in KDC system electric current of the ionisation chamber at multiple moment in the channel RPN；
Current calculation unit, for calculating ionisation chamber current average according to the electric current.
Optionally, certificate parameter determining module 20 further include:
Second parameter acquisition module is averaged for obtaining the ionisation chamber electric current in KIT system or KIC system in the channel RPN
Value acquires the current power conversion coefficient of RPN system；
Second is averaged power computation module relatively, calculates core function according to the ionisation chamber electric current and current power conversion coefficient
The opposite mean power of rate；
2nd GkCertificate parameter module, for according to the opposite mean power of the core power and passing through test-meter system
The thermal power variable of acquisition determines GkCertificate parameter.
Optionally, the implementation condition of the thermal power acquiring unit includes:
Nuclear island and conventional island are in steady working condition at least 2 hours；
Mains frequency: 49.8≤F≤50.2；
Steam generator water level is stablized, and automatic adjustment state is in, and water level is no more than 5% in the variation of narrow range instrument；
Steam generator feedwater flow is stablized；
Voltage-stablizer pressure and stable level, and it is in automatic control mode；
Core power is higher than core thermal power, and the not super default control limit value of core power peak, while testing preceding specified time
Interior completion reduces secondary circuit load and dilution, and control reactor core persistently overheats approach and not super assigned temperature value；
Reactor coolant mean temperature and reference temperature difference absolute value are less than 0.5 DEG C；
Steam generator blowdown system blowdown flow is stablized；
RPN system, KIT system, KME system, KDC system, LSS system are in available mode.
Embodiment three:
The third aspect of the embodiment of the present application provides a kind of computer readable storage medium, the computer-readable storage
Media storage has computer program, realizes that above-mentioned pressurized water reactor heap outer core such as is surveyed when the computer program is executed by processor
The G of amount systemkThe step of parameter verification method.
In the above-described embodiments, it all emphasizes particularly on different fields to the description of each embodiment, is not described in detail or remembers in some embodiment
The part of load may refer to the associated description of other embodiments.
Embodiment described above is only to illustrate the technical solution of the application, rather than its limitations；Although referring to aforementioned reality
Example is applied the application is described in detail, those skilled in the art should understand that: it still can be to aforementioned each
Technical solution documented by embodiment is modified or equivalent replacement of some of the technical features；And these are modified
Or replacement, the spirit and scope of each embodiment technical solution of the application that it does not separate the essence of the corresponding technical solution should all
Comprising within the scope of protection of this application.
Claims (17)
1. a kind of G of pressurized water reactor out-pile nuclear measurement systemkParameter verification method characterized by comprising
G is determined according to the thermal power variable of test-meter systemkParameter；
G is determined according to the ionisation chamber electric current in the channel RPNkCertificate parameter；
Judge the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than preset threshold；
If the absolute value of the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
2. the G of pressurized water reactor out-pile nuclear measurement system according to claim 1kParameter verification method, which is characterized in that
It is described that G is determined according to the thermal power variable of test-meter systemkParameter includes:
The test of test-meter system heat balance is carried out, thermal power variable is obtained by test-meter system；
Obtain the opposite average core power of RPN channel measurement；
According to the thermal power variable, opposite average core power and G 'kParameter calculates GkParameter, the G 'kParameter is thermal balance
G before testkParameter.
3. the G of pressurized water reactor out-pile nuclear measurement system according to claim 2kParameter verification method, which is characterized in that
The opposite average core power for obtaining RPN channel measurement, comprising:
Obtain the core power at the channel RPN multiple moment in the KDC system in heat balance time section；
The average value is determined as the opposite average core by the average value for calculating the core power at the channel RPN multiple moment
Power.
4. the G of pressurized water reactor out-pile nuclear measurement system according to claim 2kParameter verification method, which is characterized in that
The opposite average core power for obtaining RPN channel measurement, comprising:
Obtain the core power at the channel RPN multiple moment in the KIT system or KIC system in heat balance time section；
The average value is determined as the opposite average core by the average value for calculating the core power at the channel RPN multiple moment
Power.
5. the G of pressurized water reactor out-pile nuclear measurement system according to claim 3kParameter verification method, which is characterized in that
It is described that G is determined according to the ionisation chamber electric current in the channel RPNkCertificate parameter, comprising:
The ionisation chamber current average in KDC system in the channel RPN is obtained, the current power conversion coefficient of RPN system is acquired；
The opposite mean power of core power is calculated according to the ionisation chamber electric current and current power conversion coefficient；
G is determined according to the opposite mean power of the core power and the thermal power variable obtained by test-meter systemkVerifying ginseng
Number.
6. the G of pressurized water reactor out-pile nuclear measurement system according to claim 5kParameter verification method, which is characterized in that
The ionisation chamber current average obtained in KDC system in the channel RPN, comprising:
Electric current of the ionisation chamber at multiple moment in the channel RPN in acquisition KDC system；
Ionisation chamber current average is calculated according to the electric current.
7. the G of pressurized water reactor out-pile nuclear measurement system according to claim 4kParameter verification method, which is characterized in that
It is described that G is determined according to the ionisation chamber electric current in the channel RPNkCertificate parameter, comprising:
The ionisation chamber current average in KIT system or KIC system in the channel RPN is obtained, the current power of acquisition RPN system turns
Change coefficient；
The opposite mean power of core power is calculated according to the ionisation chamber electric current and current power conversion coefficient；
G is determined according to the opposite mean power of the core power and the thermal power variable obtained by test-meter systemkVerifying ginseng
Number.
8. the G of pressurized water reactor out-pile nuclear measurement system according to claim 2kParameter verification method, which is characterized in that
It is described carry out the test of test-meter system heat balance condition include:
Nuclear island and conventional island are in steady working condition at least 2 hours；
Mains frequency: 49.8≤F≤50.2；
Steam generator water level is stablized, and automatic adjustment state is in, and water level is no more than 5% in the variation of narrow range instrument；
Steam generator feedwater flow is stablized；
Voltage-stablizer pressure and stable level, and it is in automatic control mode；
Core power is higher than core thermal power, and the not super default control limit value of core power peak, while testing complete in preceding specified time
At secondary circuit load and dilution is reduced, control reactor core persistently overheats approach and not super assigned temperature value；
Reactor coolant mean temperature and reference temperature difference absolute value are less than 0.5 DEG C；
Steam generator blowdown system blowdown flow is stablized；
RPN system, KIT system, KME system, KDC system, LSS system are in available mode.
9. a kind of G of pressurized water reactor out-pile nuclear measurement systemkParameter calibrator characterized by comprising
Parameter determination module, for determining G according to the thermal power variable of test-meter systemkParameter；
Certificate parameter determining module, for determining G according to the ionisation chamber electric current in the channel RPNkCertificate parameter；
Judgment module, for judging the GkParameter and GkWhether the absolute value of the difference of certificate parameter is less than preset threshold；
Suitable modules, if the absolute value for the difference is less than preset threshold, it is determined that the GkParameter is applicable in.
10. the G of pressurized water reactor out-pile nuclear measurement system according to claim 9kParameter calibrator, which is characterized in that
The parameter determination module includes:
Thermal power acquiring unit obtains thermal power by test-meter system for carrying out test-meter system heat balance test
Variable；
Opposite average core power obtaining unit, for obtaining the opposite average core power of RPN channel measurement；
GkParameter calculation unit, for according to the thermal power variable, opposite average core power and G 'kParameter calculates GkParameter,
The G 'kParameter is the G before heat balance testkParameter.
11. the G of pressurized water reactor out-pile nuclear measurement system according to claim 10kParameter calibrator, feature exist
In the opposite average core power obtaining unit includes:
First acquisition unit, for obtaining the core power at the channel RPN multiple moment in the KDC system in heat balance time section；
First computing unit, the average value of the core power for calculating the channel RPN multiple moment determine the average value
For the opposite average core power.
12. the G of pressurized water reactor out-pile nuclear measurement system according to claim 10kParameter calibrator, feature exist
In the opposite average core power obtaining unit includes:
Second acquisition unit, for obtaining the channel RPN multiple moment in KIT system or KIC system in heat balance time section
Core power；
Second computing unit, the average value of the core power for calculating the channel RPN multiple moment determine the average value
For the opposite average core power.
13. the G of pressurized water reactor out-pile nuclear measurement system according to claim 11kParameter calibrator, feature exist
In the certificate parameter determining module includes:
First parameter acquisition module acquires RPN system for obtaining the ionisation chamber current average in KDC system in the channel RPN
Current power conversion coefficient；
First is averaged power computation module relatively, for calculating core function according to the ionisation chamber electric current and current power conversion coefficient
The opposite mean power of rate；
First GkCertificate parameter module is obtained for the opposite mean power according to the core power and by test-meter system
Thermal power variable determine GkCertificate parameter.
14. the G of pressurized water reactor out-pile nuclear measurement system according to claim 13kParameter calibrator, feature exist
In first parameter acquisition module includes:
Electric current acquiring unit, for obtaining in KDC system electric current of the ionisation chamber at multiple moment in the channel RPN；
Current calculation unit, for calculating ionisation chamber current average according to the electric current.
15. the G of pressurized water reactor out-pile nuclear measurement system according to claim 12kParameter calibrator, feature exist
In the certificate parameter determining module includes:
Second parameter acquisition module is adopted for obtaining the ionisation chamber current average in KIT system or KIC system in the channel RPN
Collect the current power conversion coefficient of RPN system；
Second is averaged power computation module relatively, calculates core power according to the ionisation chamber electric current and current power conversion coefficient
Opposite mean power；
2nd GkCertificate parameter module is obtained for the opposite mean power according to the core power and by test-meter system
Thermal power variable determine GkCertificate parameter.
16. the G of pressurized water reactor out-pile nuclear measurement system according to claim 10kParameter calibrator, feature exist
In the implementation condition of the thermal power acquiring unit includes:
Nuclear island and conventional island are in steady working condition at least 2 hours；
Mains frequency: 49.8≤F≤50.2；
Steam generator water level is stablized, and automatic adjustment state is in, and water level is no more than 5% in the variation of narrow range instrument；
Steam generator feedwater flow is stablized；
Voltage-stablizer pressure and stable level, and it is in automatic control mode；
Core power is higher than core thermal power, and the not super default control limit value of core power peak, while testing complete in preceding specified time
At secondary circuit load and dilution is reduced, control reactor core persistently overheats approach and not super assigned temperature value；
Reactor coolant mean temperature and reference temperature difference absolute value are less than 0.5 DEG C；
Steam generator blowdown system blowdown flow is stablized；
RPN system, KIT system, KME system, KDC system, LSS system are in available mode.
17. a kind of computer readable storage medium, the computer-readable recording medium storage has computer program, and feature exists
In realization pressurized water reactor heap outer core as described in any one of claim 1 to 8 is surveyed when the computer program is executed by processor
The G of amount systemkThe step of parameter verification method.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109817360A (en) * | 2019-01-22 | 2019-05-28 | 广西防城港核电有限公司 | Predict the prediction technique of nuclear heat power deviation and RPN system Gk parameter tendency |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105006262A (en) * | 2015-06-15 | 2015-10-28 | 中科华核电技术研究院有限公司 | Method for demarcating out-of-pile detector of nuclear reactor |
-
2018
- 2018-07-11 CN CN201810756467.7A patent/CN109192337B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105006262A (en) * | 2015-06-15 | 2015-10-28 | 中科华核电技术研究院有限公司 | Method for demarcating out-of-pile detector of nuclear reactor |
Non-Patent Citations (4)
| Title |
|---|
| 宋世葭: "KME对核反应堆堆芯功率的热平衡测量", 《"99全国核反应堆用核仪器学术会议论文集》 * |
| 宋世葭: "岭澳核电站计算堆芯功率的热平衡试验分析", 《核科学与工程》 * |
| 李现锋: "反应堆功率测量和功率分布监测***", 《’99全国核反应堆用核仪器学术会议论文集》 * |
| 郭城: "核电站功率控制的问题探讨", 《核安全》 * |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109817360A (en) * | 2019-01-22 | 2019-05-28 | 广西防城港核电有限公司 | Predict the prediction technique of nuclear heat power deviation and RPN system Gk parameter tendency |
| CN109817360B (en) * | 2019-01-22 | 2022-02-08 | 广西防城港核电有限公司 | Prediction method for predicting nuclear thermal power deviation and Gk parameter trend of RPN system |
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