CN103808433B - The monitoring method of nuclear power station thermal power measurement drift - Google Patents
The monitoring method of nuclear power station thermal power measurement drift Download PDFInfo
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- CN103808433B CN103808433B CN201210456761.9A CN201210456761A CN103808433B CN 103808433 B CN103808433 B CN 103808433B CN 201210456761 A CN201210456761 A CN 201210456761A CN 103808433 B CN103808433 B CN 103808433B
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Abstract
The invention discloses a kind of monitoring method of nuclear power station thermal power measurement drift, including following process：To pressure variety dQ before steam turbine one-levelSteam turbineBe monitored, and with the initial value Q in fuel recycleSteam turbineContrasted；To the variable quantity dQ of feedwater flowFeedwaterBe monitored, and with confluent QFeedwaterContrasted；According to functionMonitor function E situation of change；When the function E exceeds predetermined value, determine that measurement drift occurs in it.By the method for the present invention, achievable real-time, on-line monitoring nuclear power station thermal power measurement drift, intuitively the occurrence of presentation drift, it can accordingly take preventive measures, avoid thereby resulting in adverse consequences, ensure the safe operation of nuclear power station.
Description
【Technical field】
The present invention relates to detection technique, more particularly to a kind of detection technique suitable for the measurement drift of nuclear power station thermal power.
【Background technology】
In the nuclear power station of the various countries such as the U.S., France and China operation, with the extension of run time, core occurs frequently
The phenomenon that island thermal power occurs over-evaluating or underestimated, the appearance of this event, reduce the safety allowance that nuclear power station is run.If no
Paid attention to and solved, with the continuous drift that thermal power measures, measurement result can be presented constantly concussion and expand, or even lead
Control system collapse is caused, causes immeasurable security incident.
The main feedwater flow control of nuclear power generating sets, is the important parameter for influenceing steam generator water level regulation, directly influences
The safe and stable operation of nuclear power station.
The AND DEWATERING FOR ORIFICE STRUCTURE schematic diagram in the main feedwater flow control system pipeline of nuclear power generating sets shown in Fig. 1 is refer to, it is big sub-
Orifice plate internal diameter theoretical value 270mm is installed, according to the world in the main feedwater flow control system pipeline of Wan Ji ridges Australia nuclear power generating sets
Standard need to only be visually inspected, it is desirable to also fairly simple.International standard ISO5167-2003 advises to the correlation for the corner edge that heads on
It is set to：Upstream edge should be right angle, and angle is 90 ° ± 0.3 ° between orifice plate perforate and upstream face, angle of the face G should without wiredrawn edge,
Without flash, also without visible any exception is estimated, angle of the face G should be sharp, such as edge radius rkNo more than 0.0004d, (d is
Diameter of bore), it is believed that it is sharp.
Orifice plate angle of the face G (i.e. the sharpness of orifice plate ingress edge) will start to be destroyed after installation and operation.Make
In, due to the corrasion of fluid, especially for the fluid of high pressure or high flow rate containing particle and high-temperature steam etc., it
Ingress edge will quickly rust, be ground into round entrance edge.The result is that：Under identical flow, fluid behind aperture
Shrinkage degree weaken, differential pressure constantly reduces, and can form the negative flow error increasingly increased.The a fluid stream in orifice plate exit is minimum
Sectional area is increased after entrance is abraded, if can demarcate in this situation, it is found that the efflux coefficient of the orifice plate is
It is increased, but the less coefficient being calculated by normalized form is still continued to use in, it may appear that the negative system increasingly increased
Error.So calculating and its checking of the measurement to the corner edge that heads on to rear afterflow rate are necessary.
【The content of the invention】
The main object of the present invention is：A kind of method that can monitor the measurement drift of nuclear power station thermal power in real time is provided.
Therefore, the present invention proposes a kind of monitoring method of nuclear power station thermal power measurement drift, including following process：
To pressure variety dQ before steam turbine one-levelSteam turbineBe monitored, and with the initial value Q in fuel recycleSteam turbineCarry out pair
Than；
To the variable quantity dQ of feedwater flowFeedwaterBe monitored, and with confluent QFeedwaterContrasted；
According to functionMonitor function E situation of change；
When the function E exceeds predetermined value, judge thermal power measurement drift occurs.
Above-mentioned monitoring method, the situation of change of the function E, it is in whole fuel recycle in embodiment therein
Obtained under middle all full power mark post operating modes of monitoring.
Above-mentioned monitoring method, in embodiment therein, the predetermined value is ± 0.6.
Above-mentioned monitoring method, in embodiment therein, when the value of the function E continuously exceeds the predetermined value,
Judge thermal power measurement drift occurs.
Above-mentioned monitoring method, in embodiment therein, after it is determined that measurement drift occurs, include detecting nuclear power machine
Orifice plate in the main feedwater flow control system pipeline of group heads on the process of edge of acute angle radius.
Above-mentioned monitoring method, in embodiment therein, the head on process of edge of acute angle radius of the detection orifice plate is adopted
With three coordinate scanning survey methods, through being fitted and being calculated.
Above-mentioned monitoring method, in embodiment therein, the detection orifice plate heads on the process tool of edge of acute angle radius
Body includes：
Three coordinate scanning surveys：Orifice plate endoporus circle is divided into some equal portions, it is determined that uniform some measurement points；It is every to orifice plate
Individual head-on edge of acute angle measurement point carries out profile scanning；Gather measurement point spatial value；Obtain the pattern curve of angle of the face；
Fitting：The pattern curve of the angle of the face is fitted, it is circular to obtain head-on edge of acute angle section；
Calculate：Head-on edge of acute angle radius value is calculated as measurement point using the circular radius.
Above-mentioned monitoring method, in embodiment therein, in the calculating process, take multiple head-on edge of acute angle radiuses
The average value of measured value is as final result.
Above-mentioned monitoring method, in embodiment therein, the fitting using least square method or fitting function method,
Or trend collimation method.
Above-mentioned monitoring method, it is during the three coordinates scanning survey, orifice plate inner circle is equal in embodiment therein
It is divided into 8 equal portions, a measurement point is determined every 45 ° on circle.
Above-mentioned monitoring method, in embodiment therein, during the three coordinates scanning survey, carry out profile scanning
Sweep spacing be set as 5 microseconds.
Above-mentioned monitoring method, in embodiment therein, when the head-on edge of acute angle radius measurement meet it is following
One of or two conditions when, judge that the orifice plate is unqualified；
The average value of multiple measured values is more than 0.00032d (d is orifice plate inner diameter values)；
In the head-on edge of acute angle radius measurement, having three or more than three to be more than 0.0004d, (d is orifice plate internal diameter
Value).
Above-mentioned monitoring method, in embodiment therein, the detailed process of the fitting includes：To edge scanning curve
Handled, delete the useless point of near sharp angles, the extended line for making the side at the unilateral maximum flex point in edge is chosen, according to scanning
Circular arc is fitted, and it is circular to obtain head-on edge of acute angle section；Section is circular comprising scanning arc section, and prolongs with maximum flex point
Long line is tangent.
By the method for the present invention, real-time, on-line monitoring nuclear power station thermal power measurement drift, presentation drift directly perceived can be achieved
The occurrence of, it can accordingly take preventive measures, avoid thereby resulting in adverse consequences, ensure the safe operation of nuclear power station.
And according to measurement drift situation, can be further in time in the main feedwater flow control system pipeline of nuclear power generating sets
The orifice plate edge of acute angle radius that heads on is measured, and the sharpness of orifice plate ingress edge is quantified, can be best understood from hole
Plate changes orifice plate, so as to ensure the accurate calculating of nuclear island thermal power and unit safety in the operating state of nuclear power generating sets in time.
【Brief description of the drawings】
Fig. 1 is the AND DEWATERING FOR ORIFICE STRUCTURE schematic diagram in the main feedwater flow control system pipeline of nuclear power generating sets；
Fig. 2 is considered as the dimensionless function E of non-drifting situation curve map；
Fig. 3 is considered as the curve map of the dimensionless function E in the presence of drift situation；
The coordinate scanning survey method schematic diagrames of Fig. 4 tri-；
Fig. 5 is the datagraphic and fitting circle schematic diagram of record；
The non-ideal circular fitting circle schematic diagram of Fig. 6 upstream face serious wears；
The non-ideal circular fitting circle schematic diagram of Fig. 7 apertures inside diameter surface serious wear；
【Embodiment】
Below by specific embodiment and with reference to accompanying drawing, the present invention is described in further detail.
Embodiment one：
For nuclear power plant reactor in Power operation, its core power is all its principle on the basis of heat Balance Calculation value
To obtain reactor core power by Second Ring Road principle of energy balance.In the case of rated power operation, if to its error
Analysis carry out Correct Analysis, it is ensured that heat output of reactor can safe operation and can completely send out, meanwhile, can also find parameter
Whether fluctuation, in time diagnosis there is parameter measurement drift.
The determination of heat output of reactor and the determination of error
Heat output of reactor calculation formula is：
Wherein：
WR is reactor core (NSSS) thermal power；
W Δs Pr is the heat (MW) that other thermals source are transmitted to reactor cooling system in the unit time；
Qe is the feedwater flow of steam generator secondary circuit；
Qp is the blowdown flow of steam generator secondary circuit；
He is the feedwater enthalpy of steam generator secondary circuit；
Hp is the sewer enthalpy of steam generator secondary circuit；
Hv is the enthalpy of wet steam (kJ/kg) of steam generator secondary circuit outlet；
Hv=x Hvs+ (1-x) Hes；
X is steam generator outlet steam quality (dimensionless)；
1-x is the content (dimensionless) of steam generator outlet water from steam；
Hes is the enthalpy (kJ/kg) of saturation water；
Hvs is saturated vapor enthalpy (kJ/kg)；
The relative error of heat output of reactor is as follows：
Wherein：
Δ W heat output of reactor absolute errors；
W heat output of reactors；
The thermal power (MW) that secondary circuit working media obtains in the steam generator of WSG1, WSG2, WSG3 1,2,3；
Δ WSG1, Δ WSG2, Δ WSG3 are 1,2,3 steam generator thermal power absolute errors；
Δ W Δs Pr is other thermal source absolute errors；
Δ represents the absolute error of corresponding entry；
Footmark SG represents steam generator；In above-mentioned expression formula,Value can be considered as constant 0.25, other three
Item can be calculated with following equation：
When blowdown is closed, relational expression can be reduced to：
Thermally equilibrated possible error includes random error and systematic error：
A) calculating of random error：
The error of measured value is listed below：
◆ feed temperature error delta tARE/tARE
Wherein：
E_Pt100 is the error based on RTD
E_thermowell is the error caused by temperature survey after sleeve pipe.
E_3144 is the error based on temperature transmitter.
E_AVE is error caused by the uncertainty averaged to sampled point
E_ACQ is the error based on acquisition module, including isolated amplifier error and ADC error
NB_ACQ is number of samples；
σ is the standard deviation of measured value, and 2 σ refer to the absolute deviation values in 95% confidence level；
Footmark ARE represents feedwater.
Feed pressure error delta PARE/PARE
Wherein：
E_3051 is the error based on pressure transmitter
E_LONGTIME is long-time stability error.
E_AVE is error caused by the uncertainty averaged to sampled point.
E_ACQ is the error based on acquisition module, including isolated amplifier error and ADC error；
NB_ACQ is number of samples；
σ is the standard deviation of measured value, and 2 σ refer to the absolute deviation values in 95% confidence level.
ARE bias errors Δ (Δ PARE)/ΔPARE
Wherein：
E_3051 is the error based on pressure transmitter
E_LONGTIME is long-time stability error.
E_AVE is error caused by the uncertainty averaged to sampled point.
E_ACQ is the error based on acquisition module, including isolated amplifier error and ADC error
NB_ACQ is number of samples；
σ is the standard deviation of measured value, and 2 σ refer to the absolute deviation values in 95% confidence level.
VVP pressure error Δs PVVP/PVVP
Wherein：
E_3051 is the error based on pressure transmitter
E_LONGTIME is long-time stability error
E_AVE is error caused by the uncertainty averaged to sampled point.
E_ACQ is the error based on acquisition module, including isolated amplifier error and ADC error
NB_ACQ is number of samples；
The error of calculated value is listed below：
Wherein：
Xi represents i steam generator outlet steam qualities；
Hvsi represents i steam generator saturated vapor enthalpys (kJ/kg)；
No. i-th steam generator corresponding to small tenon i expressions, i.e., as i=1, all corresponding No. 1 steam generator ginseng of each parameter
Number.
Wherein
Then:
Error of the error of saturated vapor enthalpy from pressure measxurement, and calculate the ASME formula of water and steam thermodynamic properties
Error.Therefore：
Wherein：
Hvsi represents i steam generator saturated vapor enthalpys (kJ/kg)；
Subscript Pvi and f represent the error for coming from pressure measxurement and calculate the ASME public affairs of water and steam thermodynamic properties respectively
Formula error.
Error based on pressure measxurement is：
By being obtained after ASME formula derivations.
ASME formula errors in steam generator range of operation are 4kJ/kg, therefore：
Error of the error of saturation water enthalpy from pressure measxurement, and calculate the ASME formula of the thermodynamic properties of water and steam
Error.Therefore：
Error based on pressure measxurement is：
Derived from being obtained after ASME formula derivations.
ASME formula errors in steam generator range of operation are 0.8kJ/kg, therefore：
Because the volume modulus of water is very big, the influence of the error of pressure measxurement to the enthalpy calculation error that feeds water is just
It can be ignored.Thermometric error and ASME formula errors are only considered in the enthalpy calculation error that feeds water.Therefore：
It is based on the probabilistic error of temperature survey：
Wherein：
Te is feed temperature；
Δ te is feed temperature absolute error；
No. i-th steam generator corresponding to small tenon i expressions.
By being obtained after calculating the ASME formula derivations of feedwater enthalpy.
ASME formula errors in steam generator range of operation are 0.5kJ/kg, therefore：
According to ISO5167 (2003), the standard deviation for the enthalpy that feeds water is：
Wherein：
No. i-th steam generator corresponding to small tenon i expressions
Qe is feedwater flow；
C is efflux coefficient (dimensionless)；
β is diameter ratio (dimensionless)；
β=d/D；
D is the orifice plate diameter under operating condition；
D is operating condition downcomer circular section diameter；
ε be fluid expansion factor (dimensionless), incompressible fluid ε=1；
ρ is device upstream fluid density；
P is pressure difference (Pa)；
α is discharge coefficient (dimensionless)；
Standard deviation to the discharge coefficient of flange tapping standard orifice plate is：
According to ISO5167 (2003), incompressible fluidEqual to zero, that is to say, that：
The calculation error of pipe diameter is：
Wherein：
Subscript i represents No. i-th steam generator；
λ ' is the linear expansion coefficient of pipeline, is determined by tubing；
Di0For the actual diameter for measuring pipeline in temperature t0；
λ'T0iFor linear expansion coefficient of the pipeline in actual measurement temperature t0；
λ'TiFor linear expansion coefficient of the pipeline in operating condition temperature T；
Δ represents the absolute error of this；
It is relevant with the instrument for measuring pipeline cold conditions size.
It is relevant with the table or figure of calculating.
The calculation error of orifice plate diameter is：
Wherein：
Subscript i represents No. i-th steam generator；
λ is the linear expansion coefficient of orifice plate, is determined by sheet material；
di0For the actual diameter for measuring plate hole in temperature t0；
λt0iFor linear expansion coefficient of the plate hole in actual measurement temperature t0；
λtiFor linear expansion coefficient of the plate hole in operating condition temperature T；
Δ represents the absolute error of corresponding entry
It is relevant with the instrument of measuring diaphragm cold conditions diameter, if orifice plate diameter is revised value.
It is relevant with the table or figure of calculating.
Because the volume modulus of water is very big, the influence of the error of pressure measxurement to the enthalpy calculation error that feeds water is just
It can be ignored.Thermometric error and ASME formula errors are only considered in the enthalpy calculation error that feeds water.Therefore：
It is based on the probabilistic error of temperature survey：
By being obtained after calculating the ASME formula derivations of feedwater enthalpy.
ASME formula errors in steam generator range of operation are 410-7m3/ kg, therefore：
Wherein：
Small tenon i represents No. i-th steam generator
V is specific volume
Δ represents the absolute error of corresponding entry
According to above formula, the margin of error of heat output of a reactor and every calculating parameter can be obtained.
Record electric signal outranges situation while calculating reactor capability, and super electricity journey is carried out to the electric signal after conversion
Check, determine that the mass property of data is as follows：
● good data：In range ability
● suspicious data：More than electricity journey but in allowed band
● invalid data：Super electricity journey exceedes allowed band
0%, 2%, 5% and 10%4 grades that super electricity journey allowed band is signal full range are set, to it is invalid with can
The data of doubtful collection are rejected, and provide rejecting ratio be more than 5% when, signal confidence level, which is reduced to, to be needed to investigate, early warning
Power excursion.
During unit operation, by supervising unit operational factor, nuclear island power excursion is judged whether.Specific method
Be during operation, the variable quantity of pressure before the steam turbine one-level of secondary circuit monitored, and with it is initial in fuel recycle
Value is contrasted, with the ratio of pressure before the variable quantity and one-level of feedwater flow, it is determined whether generation and power excursion.
Flow-rate ratio is before and after can obtaining variable working condition by Fu Liugeer Flugel formula:
From Fu Liugeer formula, (1) derived (2) formula, the feature expression as through-current capability:
Wherein：
T is temperature
P is pressure
G is flow
Subscript 0 refers to parameter before level, and subscript Z refers to parameter after level
Fu Liugeer has made that one is basic it is assumed that i.e. flow area keeps constant, once and circulation area changes,
Above-mentioned relation formula is invalid.
As can be seen here, if the flow area of unit keeps constant, in the case where ignoring temperature change, the pressure of adjacent level group
Power ratio keeps constant when variable working condition.This can be used as detecting whether turbine flow passage component failure is damaged or fouling
Foundation, otherwise the accuracy of nuclear island thermal power can be examined.If the front and rear pressure ratio of certain grade of group is changed, this grade of group
Aisle spare is changed or flow measurement of steam changes.
This load of general nuclear power station unit station tape base, while the evaporator of nuclear power station is stricter than conventional thermoelectricity to water quality requirement,
Fouling and corrosion will not occur in the whole service cycle for blade, through-flow to change, it is possible to public using Fu Liugeer
Formula, worst error source feedwater flow in KME is verified by monitoring section pressure change before and after daily or overhaul（Steam flow）
Accuracy.
To ensure that precision is accurate, verification condition requires unit band base load, in the cycle of operation or overhaul former and later two works
Condition thermal power（Flow）It is identical or close.
Based on substantial amounts of nuclear steam turbine service data, to formula（2）Before and after overhaul or the operating mode of the cycle of operation it is steady
It is qualitative to be verified, it fact proved, its stability is very high（About 0.1%）, especially steam turbine high-pressure cylinder first paragraph, according to
Formula is we have found that cross APG blowdown flow problems（0.2%）.
Therefore, by formula（2）F names be characterized flow area, as the sign of through-flow level segment performance, choose just
Regular data obtains F, compares therewith during operation or before and after overhaul, can verify the accuracy of KME flows.
In fact, close under the conditions of rated heat input, rated heat load, high pressure cylinder is saturated vapor, and two working temperatures vary less,
Fu Liugeer Flugel formula can be reduced to：
The feature expression of through-current capability can be reduced to：
Fj=G/P0（4）
To formula（4）Stability also verified that fact proved, its stability is also very high（About 0.2%）.
From analysis above, as long as the value of each extraction pressure of steam turbine can accurately be measured, and unit head is grasped
Extraction pressure value during secondary operation or after certain overhaul under each main steam flow, it is possible to relatively accurately obtain the steam turbine
The feature expression of through-current capability, the accuracy of nuclear island thermal power is verified.
It is directly proportional to the steam flow for entering steam turbine by the power discussed above for understanding steam turbine, and pressure is before one-level
Reflect the characteristic parameter of steam turbine flow, therefore establish dimensionless functionIn whole fuel recycle,
Supervise the situation of change of all full power mark post operating modes.Specific supervision situation works as dimensionless as illustrated, refer to shown in Fig. 2
Function E value in the range of -0.4 to 0.4 always when drifting about and without departing from warning value ± 0.6, it was demonstrated that measurement drifts in conjunction
Within the scope of reason, permission, measurement result can be used directly, be considered as and exist without measurement drift situation；Now, make without for this
Further processing, detection or maintenance shut-downs etc..Refer to shown in Fig. 3, when dimensionless function E value repeatedly beyond warning value ±
When 0.6, it was demonstrated that measurement drift is considered as in the presence of drift situation, if measurement result quilt now beyond scope that is reasonable, allowing
Directly use, by the amplification of control system, necessarily cause control system to take self-protection measure, nuclear power station is therefore non-
Orderly closedown, bring huge operation loss and potential safety hazard.Now it is necessary to take an immediate action, check related sensor and
Nuclear island instrumentation, verify whether that nuclear island power measurement value drift really occurs.And in overhaul emphasis check orifice plate and other
Relevant device.
Most sensor and nuclear island instrumentation, measurement drift whether can occur with On line inspection, and take compensation
Or remedial measure.But the orifice plate in steam turbine flow detection, On line inspection can not be carried out, can only be checked in overhaul.
Because orifice plate is high temperature resistant, high pressure, the metal material corroded, orifice plate is arranged in machine set system, ingress edge meeting
Abraded quantity by fluid is fairly small.Can to the data measured for the edge of acute angle radius that heads on by (lasting several years) for a long time
Know, orifice plate can become big year by year with the increase of the on-line operation time limit, head-on edge of acute angle radius, but most data is concentrated and divided
Cloth is in the range of (0.010-0.108) mm.In order to measure so small radius value, the present embodiment using three coordinate measuring machine and
Measuring machine three-dimensional coordinates measurement software carries out the measurement and fitting of head-on edge of acute angle radius, and has formulated head-on edge of acute angle radius
Whether the judge of satisfaction requirement requires.
The limits of error of the three coordinate measuring machine used in work are ± (1.5+3L/1000) μm, and wherein L is measurement
Length, unit mm.Actual measurement length, three-dimensional coordinates measurement in the calibration certificate provided according to the third-party institution and work
The measurement error of machine is less than 1 μm.
Measuring method using being three coordinate scanning survey methods, rely primarily on be three coordinate measuring machine probe with high precision scanning
Function.Specific measuring method is that orifice plate endoporus circle is divided into 8 parts, a measurement point is determined every 45 ° on circle, uses
To flow-through orifice, each head-on edge of acute angle measurement point carries out profile scanning, scanning direction edge to the scanning feeler of three coordinate measuring machine
In figure " direction one " to " direction two " move, as shown in Figure 4.And determining appropriate sweep spacing, i.e., measuring machine often passes through one
Individual sweep spacing gathers a coordinate value.The shape to form angle of the face is fitted using the space coordinates of three coordinate measuring machine measured value
Curve, head-on edge of acute angle radius r is calculated by softwarekValue, seek its 8 rkThe average value of value, in this, as head-on sharp
Corner edge radius rkFinal result.
In measuring machine set profile scanning program, the sweep spacing of measuring machine is set as 5 μm, make scanning feeler along
Each head on edge of acute angle section gathered data successively.Record data in scanning process, and form the edge of acute angle section that heads on
Scan pattern.The circular shape obtained according to scanning, artificially choose suitable arc section and carry out least square fitting, it is final to obtain
Circular to head-on edge of acute angle section, headed on edge of acute angle radius value r using the radius of circle as measurement pointk, as shown in Figure 5.
Head-on edge of acute angle scanning patter shown in Fig. 5 is close to preferable state after it wears in a fluid.But scene
The flow regime of fluid is complicated in pipeline, while may be mingled with impurity in fluid, the mill of this edge of acute angle that headed on to orifice plate
Damage degree brings very big uncertainty.According to conventional measurement experience, the degree of wear of most head-on edge of acute angle is all
Substantially deviate from perfect condition.
Two kinds of typical non-ideal circular arcs in head-on edge of acute angle scanning patter shown in Fig. 6 and Fig. 7, Fig. 6 scanning figure
Shape indicates the upstream face of orifice plate by the more serious of fluid abrasion, causes upstream face to lack one piece；And Fig. 7 scanning patter
The more serious of orifice plate inside diameter surface abrasion is then indicated, causes aperture surface to lack one piece.
Head-on the measurement overall process of edge of acute angle is carried out automatically according to the program of setting by three coordinate measuring machine, artificially
The error brought into can be neglected, and finally head on edge of acute angle radius value rkThe whether accurate side for only relying on artificial fitting circle
Method.In order to formed the orifice plate of nuclear power generating sets head on edge of acute angle section circle fitting method, it is non-for two kinds in Fig. 6 and Fig. 7
Perfect condition, the matching rule that this example is justified using head-on edge of acute angle section：Edge scanning curve is handled, deletes acute angle
Neighbouring useless point, the extended line for making the side at the unilateral maximum flex point in edge is chosen, is fitted, is fitted according to scanning circular arc
Circle need to include scanning arc section as far as possible, and tangent with the extended line of maximum flex point, be met using the radius value of the circle as orifice plate
Face edge of acute angle radius value.
Justified by measurement and artificial fitting, obtain 8 rkValue, final head-on edge of acute angle radius value rkIt is worth for this 8
Average value.
Complete measurement and fitting, it will obtain 9 head-on edge of acute angle radius value rk, hole is judged according to these data
The running status of plate, this example have been formulated nuclear power generating sets and orifice plate headed on edge of acute angle radius value rkJudge rule, it is specific as follows：
1) orifice plate head on edge of acute angle should be without wiredrawn edge or flash, head-on edge of acute angle radius value rk0.0004d should be not more than,
I.e.≤0.108mm, is generally available and visually observes, and examines edge not the reflected beams, it is also possible to other equipment measurement edge half
Footpath；
2) head on edge of acute angle radius value rkUnderproof decision principle：
A) there are 3 values to be more than 0.0004d in 8 values (d is orifice plate inner diameter values)；
B) average value is more than 0.00032d (d is orifice plate inner diameter values).
By this example, the measurement drift of real-time oversight nuclear power station thermal power, the occurrence of drift is presented directly perceived can be achieved；One
There is drift situation in denier, can detecting system accordingly various kinds of sensors, and utilize overhaul opportunity detection flows orifice plate, in time more
Orifice plate is changed, avoids thereby resulting in adverse consequences.And according to measurement drift situation, in time to the orifice plate of steam turbine flow control system
Head-on edge of acute angle radius is measured, and the sharpness of orifice plate ingress edge is quantified, and can be best understood from orifice plate and be existed
The operating state of nuclear power generating sets, changes orifice plate in time, so as to ensure the accurate calculating of nuclear island thermal power and unit safety.
Above content is to combine specific preferred embodiment further description made for the present invention, it is impossible to is assert
The specific implementation of the present invention is confined to these explanations.For general technical staff of the technical field of the invention,
On the premise of not departing from present inventive concept, some simple deduction or replace can also be made, should all be considered as belonging to the present invention's
Protection domain.Such as the teaching by the embodiment of the present invention, skilled person will appreciate that, the fitting in embodiment can be with
The methods of using function method, trend collimation method；Setting of selection, sweep spacing for measurement point etc., accommodation can also be made.
Claims (13)
1. a kind of monitoring method of nuclear power station thermal power measurement drift, including following process：
To pressure variety dQ before steam turbine one-levelSteam turbineBe monitored, and with the initial value Q in fuel recycleSteam turbineContrasted；
To the variable quantity dQ of feedwater flowFeedwaterBe monitored, and with confluent QFeedwaterContrasted；
According to functionMonitor function E situation of change；
When the function E exceeds predetermined value, judge thermal power measurement drift occurs.
2. monitoring method as claimed in claim 1, it is characterized in that：The situation of change of the function E, it is in whole fuel recycle
Obtained under middle all full power mark post operating modes of monitoring.
3. monitoring method as claimed in claim 1, it is characterized in that：The predetermined value is ± 0.6.
4. monitoring method as claimed in claim 1, it is characterized in that：When the value of the function E continuously exceeds the predetermined value, sentence
Surely thermal power measurement drift occurs.
5. such as the monitoring method any one of claim 1-4, it is characterized in that：After judging to occur measurement drift, also wrap
The orifice plate in the detection main feedwater flow control system pipeline of nuclear power generating sets is included to head on the process of edge of acute angle radius.
6. monitoring method as claimed in claim 5, it is characterized in that：The head on process of edge of acute angle radius of the detection orifice plate is adopted
With three coordinate scanning survey methods, through being fitted and being calculated.
7. monitoring method as claimed in claim 6, it is characterized in that：It is described detection orifice plate head on edge of acute angle radius process tool
Body includes：
Three coordinate scanning surveys：Orifice plate endoporus circle is divided into some equal portions, it is determined that uniform some measurement points；Orifice plate is each met
Face edge of acute angle measurement point carries out profile scanning；Gather measurement point spatial value；Obtain the pattern curve of angle of the face；
Fitting：The pattern curve of the angle of the face is fitted, it is circular to obtain head-on edge of acute angle section；
Calculate：Head-on edge of acute angle radius value is calculated as measurement point using the circular radius.
8. monitoring method as claimed in claim 7, it is characterized in that：In the calculating process, multiple head-on edge of acute angle half are taken
The average value of footpath measured value is as final result.
9. monitoring method as claimed in claim 7, it is characterized in that：The fitting using least square method or fitting function method,
Or trend collimation method.
10. monitoring method as claimed in claim 7, it is characterized in that：During the three coordinates scanning survey, by orifice plate inner circle
8 equal portions are divided into, a measurement point is determined every 45 ° on circle.
11. monitoring method as claimed in claim 7, it is characterized in that：During the three coordinates scanning survey, carry out section and sweep
The sweep spacing retouched is set as 5 microseconds.
12. monitoring method as claimed in claim 7, it is characterized in that：When it is described head-on edge of acute angle radius measurement meet with
It is one of lower or two conditions when, judge that the orifice plate is unqualified；
The average value of multiple measured values is more than 0.00032d, and d is orifice plate inner diameter values；
In the head-on edge of acute angle radius measurement, there are three or more than three to be more than 0.0004d, d is orifice plate inner diameter values.
13. monitoring method as claimed in claim 9, it is characterized in that：The detailed process of the fitting includes：It is bent to boundary scan
Line is handled, and is chosen the extended line for making the side at the unilateral maximum flex point in edge, is fitted, is met according to scanning circular arc
Face edge of acute angle section is circular；Section is circular to include scanning arc section, and tangent with the extended line of maximum flex point.
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| CN109065198B (en) * | 2018-07-11 | 2020-03-03 | 岭澳核电有限公司 | Nuclear power unit power boost margin monitoring method, device and system |
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Address after: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city Guangdong province 518031 17 19 floor Applicant after: China General Nuclear Power Corporation Applicant after: Dayawan Nuclear Power Running Management Co., Ltd. Address before: Shenzhen science and technology building, No. 1001 Futian District Road, Shenzhen city Guangdong province 518031 17 19 floor Applicant before: China Guangdong Nuclear Power Group Co., Ltd. Applicant before: Dayawan Nuclear Power Running Management Co., Ltd. |
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