CN109243643A - Nuclear power plant evaporator steam flow redundant measurement channel comparative approach and system - Google Patents
Nuclear power plant evaporator steam flow redundant measurement channel comparative approach and system Download PDFInfo
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The present invention relates to nuclear power plant evaporator steam flow redundant measurement channel comparative approach and systems, comprising the following steps: S1, is formulated using uncertainty mean square root method and intersects standard of comparison；S2, the real-time steam flow value for acquiring steam flow redundant measurement channel；S3, average value processing is carried out to real-time steam flow value collected, obtains the measurement average value in steam flow redundant measurement channel, the reference value that the measurement average value in steam flow redundant measurement channel is compared as intersection；S4, the real-time steam flow value of all acquisitions is compared operation with the reference value, by comparison operation result compared with prepared intersection standard of comparison carries out intersection.Implementing the present invention can be with the exception or failure of the steam channel of online verification nuclear power plant evaporator; and respective handling movement is executed according to verification result; it is not involved in process channel and maintains system and functions of the equipments normal, effectively improve the availability of nuclear power plant evaporator important equipment and function.
Description
Technical field
The present invention relates to nuclear power plant evaporator fields, superfluous more specifically to a kind of nuclear power plant evaporator steam flow
Remaining Measurement channel comparative approach and system.
Background technique
Nuclear power station meets diversity, redundancy and independency principle in initial designs, and use is identical, redundancy or equivalent
Mode measures same measurement object, and evaporator (steam generator) steam flow of nuclear power station is typical tested pair
As.
Although Redundancy Design improves the reliability of equipment and function, while increasing the maintenance of equipment.Especially
Be how effectively to judge when deviation occurs in the measuring device in redundant measurement evaporator steam flow Measurement channel whether
There are exceptions or failure to become existing nuclear power station urgent problem.
Summary of the invention
The technical problem to be solved in the present invention is that in view of the above drawbacks of the prior art, providing a kind of nuclear power station evaporation
Device steam flow redundant measurement channel comparative approach and system.
The technical solution adopted by the present invention to solve the technical problems is: it is superfluous to construct a kind of nuclear power plant evaporator steam flow
Remaining Measurement channel comparative approach, the steam flow redundant measurement channel applied to nuclear power plant evaporator, comprising the following steps:
S1, it is formulated using uncertainty mean square root method and intersects standard of comparison；
S2, the real-time steam flow value for acquiring steam flow redundant measurement channel；
S3, average value processing is carried out to real-time steam flow value collected, obtains the survey in steam flow redundant measurement channel
Average value is measured, the reference value that the measurement average value in steam flow redundant measurement channel is compared as intersection；
S4, the real-time steam flow value of all acquisitions is compared operation with the reference value, by comparison operation result
Compared with prepared intersection standard of comparison carries out intersection.
Preferably, the intersection standard of comparison includes:
Small flow excision point and stripped deviation and measurement are up to the tolerance standard under maximum deviation stagnation condition；
Tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety；
Tolerance standard under the conditions of reactor protection channel function allowable error.
Preferably, if the intersection standard of comparison are as follows: under the conditions of the uncertainty of steam flow redundant measurement channel entirety
Tolerance standard；
The step S1 includes:
S11, the relational expression for obtaining flow and differential pressure；
S12, according to the relationship of steam flow channel operating condition and vapour density and pressure and flow and differential pressure are combined
Relational expression calculates the uncertainty of steam flow differential pressure measurement；
S13, to the uncertainty and all modules of Measurement channel for calculating resulting steam flow differential pressure measurement not really
Fixed degree is calculated, and the uncertainty of steam flow redundant measurement channel entirety is obtained；
S14, the uncertainty of resulting steam flow redundant measurement channel entirety will be calculated from multiplied by setting coefficient, acquisition
Tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety.
Preferably, the step S13 includes:
Uncertainty and all modules of Measurement channel using error mean square root method, to the steam flow differential pressure measurement
Uncertainty carry out root mean square operation, obtain the uncertainty of steam flow redundant measurement channel entirety.
Preferably, if the intersection standard of comparison are as follows: small flow excision point and stripped deviation and measurement are up to maximum deviation
Tolerance standard under stagnation condition；
The step S1 includes:
S21, small flow excision point is set, and the not true of lower-capacity point channel entirety is calculated according to the small flow excision point
Fixed degree；
The uncertain flow theory value of S22, Acquisition channel entirety, according to the uncertain flow theory value of the channel entirety
And the practical maximum flow deviation value in redundant measurement channel, stripped deviation is calculated and measures up to maximum deviation critical point
The uncertainty in channel；
S23, the uncertainty for obtaining the lower-capacity point channel entirety and the stripped deviation and measurement are up to maximum inclined
Smaller value in the uncertainty in poor critical point channel, and the smaller value is obtained into small flow excision point multiplied by setting coefficient
And stripped deviation and measurement are up to the tolerance standard under maximum deviation stagnation condition.
Preferably, if the intersection standard of comparison are as follows: the permission under the conditions of reactor protection channel function allowable error is inclined
Poor standard；
The step S1 includes:
S31, the uncertainty for obtaining all single modules in steam flow redundant measurement channel；
S32, according to the function allowable error of measuring device and the uncertainty of all single modules, determine steam
The functional verification value in flow redundant measurement channel；
S33, the influence according to the quantity of the measuring device to deviation standard determine that reactor protection channel function allows
Tolerance standard under error condition.
Preferably, the method also includes:
According to normal distribution probability, the intersection standard of comparison is modified.
Preferably, the step S4 includes:
S41, it carries out the real-time steam flow value of all acquisitions and the reference value to make difference operation one by one, obtains each reality
When steam stream magnitude and reference value difference；
S42, the difference of each real-time steam flow value and reference value and the standard of comparison of intersecting are intersected
Compare.
Preferably, after the step S4 further include:
S5, according to intersect comparison result, judge the abnormal conditions in steam flow redundant measurement channel.
The present invention also provides a kind of nuclear power plant evaporator steam flow redundant measurement channel comparison systems, for nuclear power station
The steam flow redundant measurement channel of evaporator is compared verifying, comprising:
Determination unit intersects standard of comparison for formulating using uncertainty mean square root method；
Acquisition unit, for acquiring the real-time steam flow value in steam flow redundant measurement channel；
Reference value acquiring unit obtains steam flow for carrying out average value processing to real-time steam flow value collected
The measurement average value in redundant measurement channel compares the measurement average value in steam flow redundant measurement channel as intersection
Reference value；
Comparison operation unit, for the real-time steam flow value of all acquisitions to be compared operation with the reference value,
By comparison operation result compared with prepared intersection standard of comparison carries out intersection.
Implement nuclear power plant evaporator steam flow redundant measurement channel comparative approach and system of the invention, has with following
Beneficial effect: implementing the present invention can be with the exception or failure of the steam channel of online verification nuclear power plant evaporator, and is tied according to verifying
Fruit executes respective handling movement, is not involved in process channel and maintains system and functions of the equipments normal, effectively improves nuclear power station evaporation
The availability of device important equipment and function.
In addition, being verified by the parameter and feature characterized to system or measuring device, maintenance is thrown in personnel
Enter, repair duration, resource input etc. all few compared with Interventional maintenance, can effectively find steam flow redundant measurement channel
Exception or failure.
Detailed description of the invention
Present invention will be further explained below with reference to the attached drawings and examples, in attached drawing:
Fig. 1 is the structural schematic diagram in nuclear power station redundant measurement of the present invention channel；
Fig. 2 is the structural schematic diagram of nuclear power plant evaporator steam flow redundant measurement of the present invention；
Fig. 3 is the flow diagram of nuclear power plant evaporator steam flow redundant measurement channel of the present invention comparative approach；
Fig. 4 is the tolerance standard under the conditions of the uncertainty of present invention acquisition steam flow redundant measurement channel entirety
Program circuit schematic diagram；
Fig. 5 is that the present invention obtains small flow excision point and stripped deviation and measures up under maximum deviation stagnation condition
The program flow diagram of tolerance standard；
Fig. 6 is the program flow for the tolerance standard that the present invention obtains under the conditions of reactor protection channel function allowable error
Cheng Tu；
Fig. 7 is the schematic diagram in nuclear power plant evaporator flow measurement of steam of the present invention channel；
Fig. 8 is that nuclear power plant evaporator steam flow of the present invention channel redundant measurement intersects standard of comparison curve graph.
Specific embodiment
For a clearer understanding of the technical characteristics, objects and effects of the present invention, now control attached drawing is described in detail
A specific embodiment of the invention.
As shown in Figure 1, being the structural schematic diagram in nuclear power station exemplary traffic redundant measurement channel, wherein MD1 and MD2 is two
Road redundant measurement channel, main pipeline are equipped with restricting element, such as Venturi tube, transmitter MD1 and transmitter MD2 impression throttling member
Differential pressure before and after part exports 4~20mA current signal, which is input to cabinet progress signal processing and signal converts, and one
Road participates in display and control, and another way participates in reactor protection system (RPR), wherein display 1 and display 2 are used for real-time display
The measured value of MD1 and MD2.Wherein, Measurement channel is correspondingly arranged a measuring device all the way, and measuring device here is Fig. 1
In transmitter MD1 and transmitter MD2.
As shown in Fig. 2, nuclear power plant evaporator flow measurement of steam of the invention is provided with two-way Measurement channel, wherein every
All the way the measuring device in Measurement channel using flow redundant measurement shown in FIG. 1 channel measuring principle.
It is the flow diagram of nuclear power plant evaporator steam flow redundant measurement channel of the present invention comparative approach referring to Fig. 3.
The comparative approach is applied to the steam flow redundant measurement channel of nuclear power plant evaporator.
Specifically, as shown in figure 3, the nuclear power plant evaporator steam flow redundant measurement channel comparative approach includes following step
It is rapid:
Step S1, it is formulated using uncertainty mean square root method and intersects standard of comparison.
Due to the measurement characteristic in flow measurement channel itself, cause to measure under low power condition uncertain compared with rated power
It is lower big, so, standard of comparison is intersected in low situation using whole uncertain in flow measurement channel, and close to rated power
Under, intersect standard of comparison using nuclear power station Final Security Analysis Report (FSAR) to protection channel function allowable error under the premise of
Tolerance is calculated.
Optionally, prepared intersection standard of comparison may include: small flow excision point and theory in the embodiment of the present invention
Deviation and measurement are up to the tolerance standard under maximum deviation stagnation condition；Steam flow redundant measurement channel is whole not
Tolerance standard under the conditions of degree of certainty；Tolerance standard under the conditions of reactor protection channel function allowable error.
Specifically, each intersection standard of comparison can carry out calculating acquisition according to following manner.
As shown in figure 4, if intersecting standard of comparison are as follows: under the conditions of the uncertainty of steam flow redundant measurement channel entirety
Tolerance standard；
Step S1 includes:
Step S11, the relational expression of flow and differential pressure is obtained.
According to the measuring principle in nuclear power station exemplary traffic redundant measurement channel it is found that nuclear power station steam stream of the embodiment of the present invention
Measurement is also to be measured using the measuring principle of Fig. 1, thus, it is possible to obtain the relational expression of steam flow and differential pressure is as follows:
Wherein, Q is flow measurement of steam value；Δ P is differential pressure signal；ρ is vapor stream density.
Relational expression by above-mentioned steam flow and differential pressure is available:
And then it is available,
Wherein, Δ PMAXFor differential pressure range；QMAXFor flow range (i.e. theoretical maximum), δ is symbol of differentiating.
Step S12, according to the relationship of steam flow channel operating condition and vapour density and pressure and flow and poor is combined
The relational expression of pressure calculates the uncertainty of steam flow differential pressure measurement.
In the embodiment of the present invention, nuclear power station steam flow channel operating condition are as follows: 65~75bar, vapour density and pressure
Relationship are as follows: ρ=0.58P-4.25, ρAVG=36.6kg/m3, it can thus be seen that shadow of the vapour density to steam mass flow
Sound is larger, it is consequently possible to calculate obtaining the uncertainty of steam flow differential pressure measurement.Specific calculating process is as follows:
And then it obtains:
So the uncertainty of steam flow differential pressure measurement are as follows:
Wherein, λ1For the uncertainty coefficient of differential pressure (Δ P) measurement；QSTFor the measurement average value of steam flow；δQST′For
The uncertainty flow value (t/h) of steam flow Δ P measurement；εST′For the uncertainty percentage of steam flow Δ P measurement
(%).It is to be appreciated that in order to unified, the uncertainty of steam flow differential pressure measurement mentioned herein refers to steam flow Δ P
The uncertainty percentage of measurement.
Step S13, to the uncertainty and all modules of Measurement channel for calculating resulting steam flow differential pressure measurement
Uncertainty is calculated, and the uncertainty of steam flow redundant measurement channel entirety is obtained.
Optionally, in this step, can use error mean square root method, to the uncertainty of steam flow differential pressure measurement with
And the uncertainty of all modules of Measurement channel carries out root mean square operation, obtains the not true of steam flow redundant measurement channel entirety
Fixed degree.
Wherein, the uncertainty of all modules of Measurement channel can operation instructions directly according to used module it is direct
It obtains.After the uncertainty for obtaining steam flow differential pressure measurement in step s 13, in conjunction with the not true of all modules of Measurement channel
Fixed degree carries out root mean square operation using error mean square root method, can be obtained the uncertain of steam flow redundant measurement channel entirety
Degree.
It can specifically be obtained by following calculating formula:
Wherein, εSTFor the uncertainty (%) of steam flow redundant measurement channel entirety；ε1、ε2、……、εkFor steam stream
Measure the uncertainty of single module in redundant measurement channel, the quantity for the module that k includes by steam flow redundant measurement channel.
Step S14, the uncertainty of resulting steam flow redundant measurement channel entirety will be calculated from multiplied by setting coefficient,
Obtain the tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety.
Optionally, as can be seen from FIG. 2, steam flow of embodiment of the present invention redundant measurement channel is two, so, it is obtaining
After the uncertainty of steam flow redundant measurement channel entirety, also need to carry out side's processing, i.e., multiplied by setting coefficient.Wherein, if
Determining coefficient isTherefore, the tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety is with mathematics
Expression formula indicates are as follows:
As shown in figure 5, if intersecting standard of comparison are as follows: small flow excision point and stripped deviation and measurement are faced up to maximum deviation
Tolerance standard under the conditions of boundary's point；Then step S1 may include:
Step S21, the small flow excision point of setting, and point is cut off according to small flow and calculates the not true of lower-capacity point channel entirety
Fixed degree.
By steam flow it can be seen from the relational expression of aforementioned flow and differential pressure, there are the relationships of evolution with differential pressure, therefore,
It is larger to carry out small signal errors when extracting operation, so, when carrying out intersecting standard of comparison formulation, compare mark to guarantee to intersect
Quasi- validity, need to be arranged flow dead zone, that is, small flow excision point is arranged.
Specifically, small flow excision point indicates that the real-time steam flow value of real-time measurement is with α in the embodiment of the present invention
QST, theoretical maximum QMAX, wherein α is percentage.Point is cut off due to being provided with small flow, so, when real-time steam flow value
QST< α × QMAXWhen, flow indication 0；As real-time steam flow value QST≥α×QMAXWhen, flow indication is current measurement
Value.Therefore, as real-time steam flow value QST< α × QMAXWhen, the uncertainty value to steam flow channel entirety is QSTa=α
×QMAX, when so as to which small flow excision point is calculated, the uncertainty of steam flow channel entirety, i.e.,
Wherein, εSTaThe uncertainty of steam flow channel entirety when cutting off point for small flow.
Step S22, the uncertain flow theory value of Acquisition channel entirety, according to the uncertain flow theory value of channel entirety
And the practical maximum flow deviation value in redundant measurement channel, stripped deviation is calculated and measures up to maximum deviation critical point
The uncertainty in channel.
The uncertainty theory value of flow measurement of steam channel entirety can be obtained by the following formula:
εST×QMAX。
Additionally, it is contemplated that steam flow redundant measurement is logical when stripped deviation and measurement are up under maximum deviation stagnation condition
The practical maximum flow deviation value in road are as follows:
|QSTj-QSTj+1|MAX=n × QST；
Wherein, QSTjFor the show value of one of measuring device measurement, n is the quantity of measuring device, QSTFor steam flow
Measurement average value (t/h).
Enable n × QST=εST×QMAX, stripped deviation is calculated and measures the uncertainty up to maximum deviation critical pointAnd measure the steam stream magnitude Q of reachable maximum deviation critical pointSTb。
Step S23, the uncertainty of acquisition lower-capacity point channel entirety and stripped deviation and measurement are faced up to maximum deviation
Smaller value in the uncertainty in boundary point channel, and smaller value is obtained into small flow excision point and theory partially multiplied by setting coefficient
Difference and measurement are up to the tolerance standard under maximum deviation stagnation condition.
Optionally, setting coefficient can beSo small flow excision and stripped deviation and measurement are up to maximum inclined
Tolerance standard under poor stagnation condition can be indicated with mathematic(al) representation are as follows:
As shown in fig. 6, if intersecting standard of comparison are as follows: the tolerance under the conditions of reactor protection channel function allowable error
Standard；Then step S1 may include:
Step S31, the uncertainty of all single modules in steam flow redundant measurement channel is obtained.
The uncertain of all single modules in steam flow redundant measurement channel is each single module itself
Measurement accuracy can be directly obtained by the operation instructions of each single module.
Step S32, according to the function allowable error of measuring device and the uncertainty of all single modules, steam is determined
The functional verification value in flow redundant measurement channel.
The function allowable error of measuring device can be obtained by the following formula:
δ (FS)=(δ (FP)2-δ(FT)2)1/2；
It is obtained in conjunction with the uncertainty progress root mean square operation of all single modules:
Wherein, δ (FS)=(δ (FP)2-δ(FT)2)1/2。
ε (fv) is the functional verification value in steam flow redundant measurement channel, and δ (FS) is that the function of measuring device allows to miss
Difference, εj、εj+1..., for the uncertainty of all single modules in steam flow redundant measurement channel, δ (FP) is channel function
Allowable error, wherein channel function allowable error δ (FP) is at the function allowable error δ (FS) and channel signal of measuring device
The summation of the function allowable error δ (FT) of part is managed, i.e.,
By making ε (fv)=εST, uncertainty and the channel of steam flow redundant measurement channel entirety can be calculated
The flow value Q in function allowable error crosspointZ.When less than QZWhen, illustrate that uncertainty existing for the overall objective of channel is greater than channel
Function allowable error, so using the uncertainty of channel entirety as intersection standard of comparison；When greater than QZWhen, illustrate channel entirety
The uncertainty of objective reality is less than channel function allowable error, so comparing mark using channel function allowable error as intersection
It is quasi-.
Step S33, the influence according to the quantity of measuring device to deviation standard determines that reactor protection channel function allows
Tolerance standard under error condition.
Specifically, the reference measure precision of each measuring device is ε (t), it is assumed that the coefficient of measuring device number is X,
Then the tolerance standard under the conditions of available reactor protection channel function allowable error is indicated with mathematic(al) representation are as follows:
The quantity of measuring device is more it can be seen from the formula, and degree of redundancy is got over
Height then illustrates that the confidence level of reference value is higher, can suitably relax standard.
Wherein, coefficient X and the corresponding relationship of measuring device (redundant sensor) number are as follows:
Through the above scheme, it may finally determine that the intersection standard of comparison in steam flow redundant measurement channel can with mathematical expression
To indicate are as follows:
As the measurement average value Q of steam flow it can be seen from the formulaSTStream when point is cut off less than or equal to small flow
Magnitude QSTaWith the Q for measuring reachable maximum deviation critical pointSTbIn the larger value when, then with small flow cut off point and stripped deviation and
It measures up to the tolerance standard under maximum deviation stagnation condition as intersection standard of comparison；As measuring flow average value QST
Less than channel entirety uncertainty and the flow value Q in channel function allowable error crosspointZ, and be greater than when the excision of small flow is put
Flow value QSTaWith the Q for measuring reachable maximum deviation critical pointSTbIn the larger value when, then it is whole with steam flow redundant measurement channel
Tolerance standard under the conditions of the uncertainty of body is as intersection standard of comparison；As measuring flow average value QSTIt is greater than or equal to
The flow value Q in channel entirety uncertainty and channel function allowable error crosspointZWhen, then permitted with reactor protection channel function
Perhaps the tolerance standard under error condition is as intersection standard of comparison.
Further, in embodiments of the present invention, it in order to keep prepared intersection standard of comparison precision higher, can use
Normal distribution probability is modified prepared intersection standard of comparison.
It is μ=0, σ according to parameter specifically, being analyzed according to normal distribution probability2The normal distribution of (σ is standard deviation)
Probability density function:
Wherein, x is the uncertainty in steam flow redundant measurement channel, when -1.96 σ≤σ of x≤+ 1.96, normal distribution letter
Number Φ (x)=95% can meet the determination requirement of flow measurement of steam channel availabity in this section according to design standard, therefore enable
1.96 σ=C (fv).Different flow measurement channels have differences in harsh degree, therefore, can be according to normal distribution probability point
Analysis sets C (fv) coefficient, realizes abnormal and breakdown judge cover probability.
Step S2, the real-time steam flow value in steam flow redundant measurement channel is acquired.
The real-time steam flow value in steam flow redundant measurement channel include it is multiple, it is specifically true with set measuring device
It is fixed, i.e. the corresponding real-time steam flow value of a measuring device.Assuming that there is n measuring device, then real-time steam collected
Flow value are as follows: QST1、QST2、QST3、……、QSTn。
Step S3, average value processing is carried out to real-time steam flow value collected, obtains steam flow redundant measurement channel
Measurement average value, using the measurement average value in steam flow redundant measurement channel as the reference value that compares of intersection.
The measurement average value in steam flow redundant measurement channel can be indicated with mathematic(al) representation are as follows:
S4, the real-time steam flow value of all acquisitions is compared operation with reference value, by comparison operation result and institute
The intersection standard of comparison of formulation carries out intersection comparison.
Optionally, in the embodiment of the present invention, step S4 may include:
Step S41, it carries out the real-time steam flow value of all acquisitions and reference value to make difference operation one by one, obtains each reality
When steam stream magnitude and reference value difference.
Step S42, by each real-time steam flow value with the difference of reference value compared with intersecting standard of comparison and intersect.
Further, can also include: after step S4
Step S5, according to comparison result is intersected, judge the abnormal conditions in steam flow redundant measurement channel.
Specifically, by real-time steam magnitude Q collectedST1、QST2、QST3、……、QSTnIt is surveyed one by one with steam flow redundancy
Measure the measurement average value Q in channelSTIt is compared, if beyond standard of comparison is intersected, such asThen illustrate
QST1There is exception in corresponding vapour survey channel, need further progress inspection and processing, or take the maintenance side of Interventional
Formula.Conversely, ifThen illustrate QST1Corresponding Measurement channel deviation is within allowed band, as a result
Qualification is not required to handle.
The present invention also provides a kind of nuclear power plant evaporator steam flow redundant measurement channel comparison systems, for nuclear power
The stand steam flow redundant measurement channel of evaporator is compared verifying, which can be used for realizing above-mentioned nuclear power station evaporation
Device steam flow redundant measurement channel comparative approach, specifically, the comparison system may include:
Determination unit 10 intersects standard of comparison for formulating using uncertainty mean square root method；
Acquisition unit 20, for acquiring the real-time steam flow value in steam flow redundant measurement channel；
Reference value acquiring unit 30 obtains steam stream for carrying out average value processing to real-time steam flow value collected
The measurement average value for measuring redundant measurement channel, the ginseng that the measurement average value in steam flow redundant measurement channel is compared as intersection
Examine value；
Comparison operation unit 40 will for the real-time steam flow value of all acquisitions to be compared operation with reference value
Comparison operation result is compared with prepared intersection standard of comparison carries out intersection.
It can be with the exception or failure of the steam channel of online verification nuclear power plant evaporator, and according to testing by implementing the present invention
It demonstrate,proves result and executes respective handling movement, be not involved in process channel and maintain system and functions of the equipments normal, effectively improve nuclear power station
The availability of evaporator important equipment and function.
In addition, being verified by the parameter and feature characterized to system or measuring device, maintenance is thrown in personnel
Enter, repair duration, resource input etc. all few compared with Interventional maintenance, can effectively find steam flow redundant measurement channel
Exception or failure.
Technical solution of the present invention is described in detail with a concrete engineering example below.
It is specific as shown in fig. 7, being arranged for two-way redundancy, steam flow by taking nuclear power station steamer flow measurement of steam as an example
Measuring device (M) measurement restricting element before and after differential pressure signal, and convert output 4~20mA current signal, RS electric current turns voltage
4~20mA current signal is converted to 1~5V voltage signal by module.Differential pressure voltage signal carries out pressure by multiplier-divider and repairs
Just, it is then sent to DC rooting module and carries out extracting operation, participate in reactor protection logic (RPR) all the way；Another way by IS every
EU Computer display and evaporator water level control are sent from module.Wherein, MP indicates pressure transmitter in Fig. 7, and MU is multiplication and division
Device module.
The uncertainty of known differential pressure (Δ P), QMAX=2442 (t/h) set Δ P measurement according to measuring principle and characteristic
Uncertainty coefficient lambda1=1.01%, small flow cuts off point α=0.5%, and nuclear power station Final Security Analysis Report (RSAR) is right
Steam flow channel function allowable error requires to be δ (FP)=3%.
Following table is the uncertainty of each single module in vapour survey channel:
| Module | RS | DC | XU | IS | CA | EU | MU |
| Uncertainty | ε1=0.15% | ε2=0.5% | ε3=0.5% | ε4=0.5% | ε5=0.1% | ε6=0.5% | ε7=0.5% |
The uncertainty measured according to nuclear power station steam flow Δ P:
The uncertainty of steam flow redundant measurement channel entirety:
Final steam flow intersects standard of comparison C (fv) are as follows:
According to above-mentioned formula, nuclear power plant evaporator steam flow redundant measurement channel can be obtained and intersect standard of comparison song
Line, as shown in Figure 8.
Above embodiments only technical concepts and features to illustrate the invention, its object is to allow person skilled in the art
Scholar can understand the contents of the present invention and implement accordingly, can not limit the scope of the invention.It is all to be wanted with right of the present invention
The equivalent changes and modifications that range is done are sought, should belong to the covering scope of the claims in the present invention.
It should be understood that for those of ordinary skills, it can be modified or changed according to the above description,
And all these modifications and variations should all belong to the protection domain of appended claims of the present invention.
Claims (10)
1. a kind of nuclear power plant evaporator steam flow redundant measurement channel comparative approach, the steam stream applied to nuclear power plant evaporator
Measure redundant measurement channel, which comprises the following steps:
S1, it is formulated using uncertainty mean square root method and intersects standard of comparison；
S2, the real-time steam flow value for acquiring steam flow redundant measurement channel；
S3, average value processing is carried out to real-time steam flow value collected, the measurement for obtaining steam flow redundant measurement channel is flat
Mean value, the reference value that the measurement average value in steam flow redundant measurement channel is compared as intersection；
S4, the real-time steam flow value of all acquisitions is compared operation with the reference value, by comparison operation result and institute
The intersection standard of comparison of formulation carries out intersection comparison.
2. nuclear power plant evaporator steam flow redundant measurement channel according to claim 1 comparative approach, which is characterized in that
The intersection standard of comparison includes:
Small flow excision point and stripped deviation and measurement are up to the tolerance standard under maximum deviation stagnation condition；
Tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety；
Tolerance standard under the conditions of reactor protection channel function allowable error.
3. nuclear power plant evaporator steam flow redundant measurement channel according to claim 2 comparative approach, which is characterized in that
If the intersection standard of comparison are as follows: the tolerance standard under the conditions of the uncertainty of steam flow redundant measurement channel entirety；
The step S1 includes:
S11, the relational expression for obtaining flow and differential pressure；
S12, according to the relationship of steam flow channel operating condition and vapour density and pressure and combine flow and differential pressure relationship
Formula calculates the uncertainty of steam flow differential pressure measurement；
S13, the uncertainty to the uncertainty and all modules of Measurement channel that calculate resulting steam flow differential pressure measurement
It is calculated, obtains the uncertainty of steam flow redundant measurement channel entirety；
S14, the uncertainty of resulting steam flow redundant measurement channel entirety will be calculated multiplied by setting coefficient, acquisition steam stream
Measure the tolerance standard under the conditions of the uncertainty of redundant measurement channel entirety.
4. nuclear power plant evaporator steam flow redundant measurement channel according to claim 3 comparative approach, which is characterized in that
The step S13 includes:
Using error mean square root method, uncertainty and all modules of Measurement channel to the steam flow differential pressure measurement are not
Degree of certainty carries out root mean square operation, obtains the uncertainty of steam flow redundant measurement channel entirety.
5. nuclear power plant evaporator steam flow redundant measurement channel according to claim 2 comparative approach, which is characterized in that
If the intersection standard of comparison are as follows: small flow excision point and stripped deviation and measurement are up to permitting under maximum deviation stagnation condition
Perhaps deviation standard；
The step S1 includes:
S21, the small flow excision point of setting, and do not known according to the small flow excision point calculating lower-capacity point channel is whole
Degree；
The uncertain flow theory value of S22, Acquisition channel entirety, according to the uncertain flow theory value of the channel entirety and
The practical maximum flow deviation value in redundant measurement channel is calculated stripped deviation and measures up to maximum deviation critical point channel
Uncertainty；
S23, the uncertainty for obtaining the lower-capacity point channel entirety and the stripped deviation and measurement are faced up to maximum deviation
Smaller value in the uncertainty in boundary point channel, and the smaller value is obtained into small flow excision point and reason multiplied by setting coefficient
By deviation and measure up to the tolerance standard under maximum deviation stagnation condition.
6. nuclear power plant evaporator steam flow redundant measurement channel according to claim 2 comparative approach, which is characterized in that
If the intersection standard of comparison are as follows: the tolerance standard under the conditions of reactor protection channel function allowable error；
The step S1 includes:
S31, the uncertainty for obtaining all single modules in steam flow redundant measurement channel；
S32, according to the function allowable error of measuring device and the uncertainty of all single modules, determine steam flow
The functional verification value in redundant measurement channel；
S33, the influence according to the quantity of the measuring device to deviation standard, determine reactor protection channel function allowable error
Under the conditions of tolerance standard.
7. nuclear power plant evaporator steam flow redundant measurement channel according to claim 1 comparative approach, which is characterized in that
The method also includes:
According to normal distribution probability, the intersection standard of comparison is modified.
8. nuclear power plant evaporator steam flow redundant measurement channel according to claim 1 comparative approach, which is characterized in that
The step S4 includes:
S41, the real-time steam flow value of all acquisitions and the reference value are carried out to make difference operation one by one, obtains each real-time steaming
The difference of steam flow magnitude and reference value；
S42, each real-time steam flow value is intersected compared with standard of comparison intersect with the difference of reference value with described.
9. nuclear power plant evaporator steam flow redundant measurement channel according to claim 1 comparative approach, which is characterized in that
After the step S4 further include:
S5, according to intersect comparison result, judge the abnormal conditions in steam flow redundant measurement channel.
10. a kind of nuclear power plant evaporator steam flow redundant measurement channel comparison system, for the steam to nuclear power plant evaporator
Flow redundant measurement channel is compared verifying characterized by comprising
Determination unit intersects standard of comparison for formulating using uncertainty mean square root method；
Acquisition unit, for acquiring the real-time steam flow value in steam flow redundant measurement channel；
Reference value acquiring unit obtains steam flow redundancy for carrying out average value processing to real-time steam flow value collected
The measurement average value of Measurement channel, the reference that the measurement average value in steam flow redundant measurement channel is compared as intersection
Value；
Comparison operation unit will compare for the real-time steam flow value of all acquisitions to be compared operation with the reference value
Compared with operation result compared with prepared intersection standard of comparison carries out intersection.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN111982245A (en) * | 2020-07-13 | 2020-11-24 | 中广核核电运营有限公司 | Method and device for calibrating main steam flow, computer equipment and storage medium |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4957296A (en) * | 1972-07-12 | 1974-06-04 | ||
| RU1793477C (en) * | 1991-01-25 | 1993-02-07 | Научно-исследовательский и конструкторский институт энерготехники | Device for control and protection of nuclear reactor |
| CN101840740A (en) * | 2009-06-19 | 2010-09-22 | 中广核工程有限公司 | Automatic failure detection system and method for two channels |
| CN102193045A (en) * | 2010-03-19 | 2011-09-21 | 江苏核电有限公司 | Method for checking consistency of analog quantity signal channels |
| CN106782708A (en) * | 2016-11-24 | 2017-05-31 | 苏州热工研究院有限公司 | The multivariable of fluid level transmitter intersects comparative approach in a kind of amendment nuclear power station |
| CN107464591A (en) * | 2017-07-11 | 2017-12-12 | 中国核电工程有限公司 | A kind of containment leak on-line monitoring system sensor combinations optimization method |
-
2018
- 2018-08-14 CN CN201810922332.3A patent/CN109243643B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS4957296A (en) * | 1972-07-12 | 1974-06-04 | ||
| RU1793477C (en) * | 1991-01-25 | 1993-02-07 | Научно-исследовательский и конструкторский институт энерготехники | Device for control and protection of nuclear reactor |
| CN101840740A (en) * | 2009-06-19 | 2010-09-22 | 中广核工程有限公司 | Automatic failure detection system and method for two channels |
| CN102193045A (en) * | 2010-03-19 | 2011-09-21 | 江苏核电有限公司 | Method for checking consistency of analog quantity signal channels |
| CN106782708A (en) * | 2016-11-24 | 2017-05-31 | 苏州热工研究院有限公司 | The multivariable of fluid level transmitter intersects comparative approach in a kind of amendment nuclear power station |
| CN107464591A (en) * | 2017-07-11 | 2017-12-12 | 中国核电工程有限公司 | A kind of containment leak on-line monitoring system sensor combinations optimization method |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111982245A (en) * | 2020-07-13 | 2020-11-24 | 中广核核电运营有限公司 | Method and device for calibrating main steam flow, computer equipment and storage medium |
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