CN109524140A - A kind of one loop of nuclear power station abnormality tracing and monitoring method and system - Google Patents
A kind of one loop of nuclear power station abnormality tracing and monitoring method and system Download PDFInfo
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- CN109524140A CN109524140A CN201811324095.7A CN201811324095A CN109524140A CN 109524140 A CN109524140 A CN 109524140A CN 201811324095 A CN201811324095 A CN 201811324095A CN 109524140 A CN109524140 A CN 109524140A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
The invention discloses a kind of one loop of nuclear power station abnormality tracing and monitoring method and systems.The described method includes: constructing temperature and pressure run-limiting model under primary Ioops abnormality according to operation characteristic and run-limiting condition under primary Ioops abnormality；According to primary Ioops main pump operating status, the accident operating standard state and P signal state that are carrying out, corresponding primary Ioops temperature and pressure run-limiting model is selected；The operating status of primary Ioops under abnormality is obtained, and according to temperature and pressure run-limiting model under the primary Ioops abnormality of selection, adjusts the operation reserve of primary Ioops in real time.The present invention is by combining operation characteristic and run-limiting condition under primary Ioops abnormality, construct temperature and pressure run-limiting model under primary Ioops abnormality, it can assist operator's convenient operating status for intuitively monitoring primary Ioops during executing accident operating standard, suitable operation reserve is adjusted in time, is smoothly dropped back to safe condition.
Description
Technical field
The present invention relates to technical field of nuclear power, in particular to a kind of one loop of nuclear power station abnormality tracing and monitoring
Method and system.
Background technique
The large complicated device that nuclear power plant is made of hundreds of systems, to realize fuel fission reaction generation
Thermal energy is converted into the process of electric energy safely controllablely, and each system, which is endowed, undertakes specific function, such as chemistry and volumetric void fraction
System is to realize the functions such as the control of primary Ioops coolant water loading amount and the purification of primary Ioops coolant, chemistry addition.This
Putting into operation and exiting for a little system functions needs to abide by specific system operation conditions, and e.g., residual heat removal system is in primary Ioops pressure
Just allow to connect and put into operation with primary Ioops lower than 32barg and when primary Ioops temperature is lower than 120 DEG C.In fact, the operation of nuclear power plant
Need to abide by a series of run-limiting condition, these restrictive conditions or service condition determination or source according to aforementioned system
In important equipment particular requirement (for example thermal stress born of limited reactions core pressure vessel, limit primary Ioops heating and
Cooling rate is no more than 56 DEG C/h).Mean that nuclear power plant may face system equipment damage risk beyond run-limiting condition
Or potential security risk.
Primary Ioops temperature and pressure run-limiting figure under normal operating condition is by a series of unit during normal operation
Running boundary is graphically shown, is the portable tool for tracking operating states of the units, and operator is executing normal fortune
The variation path of primary Ioops parameter can be tracked clear and intuitively during the starting or stoppage in transit of professional etiquette process control unit by its and is become
Gesture is obtained mature and is widely applied in nuclear power plant at present.
However, under failure or accident conditions (reactor emergency shut-down), the primary Ioops temperature of accidental conditions and
Pressure run-limiting figure will be no longer applicable in, in fact, failure or accident conditions are often with important equipment failure or cut etc.
Representative accident needs the run-limiting condition of system function and system to be used and is operated normally under failure or accident conditions
There is also a great differences for operating condition.The evolution trend of primary Ioops parameter how has been monitored during unit recession under failure or accident conditions
One of the problem of being paid close attention to as the design of nuclear power plant's accident operating standard and man-machine interface design focal point.
Summary of the invention
In order to solve problems in the prior art, the embodiment of the invention provides a kind of tracking of one loop of nuclear power station abnormality
Monitoring method and system.The technical solution is as follows:
On the one hand, the embodiment of the invention provides a kind of one loop of nuclear power station abnormality tracing and monitoring method, the sides
Method includes:
According to the operation characteristic and run-limiting condition under preset one loop of nuclear power station abnormality, it is different to construct primary Ioops
Temperature and pressure run-limiting model under normal state；
According to the primary Ioops main pump operating status of nuclear power station, the accident operating standard state being carrying out and P signal shape
State, to select corresponding primary Ioops temperature and pressure run-limiting model, the P signal is for influencing nuclear plant safety injection system
The trigger condition of system；
The operating status of one loop of nuclear power station under abnormality is obtained, and according to temperature under the primary Ioops abnormality of selection
With pressure run-limiting model, the operation reserve of primary Ioops is adjusted in real time, until smoothly dropping back to safe condition.
In the above-mentioned one loop of nuclear power station abnormality tracing and monitoring method of the embodiment of the present invention, the abnormality packet
It includes: losing the naturally circulated condition, fault condition and accident conditions of forced circulation function.
In the above-mentioned one loop of nuclear power station abnormality tracing and monitoring method of the embodiment of the present invention, when the abnormality
When for naturally circulated condition, temperature and pressure run-limiting model includes: by water in primary Ioops under the primary Ioops abnormality
Saturation curve, primary Ioops pressure low limit line, the high restraining line of primary Ioops pressure, primary Ioops primary side of steam generator differential pressure limit
Line processed, primary Ioops steam generator secondary side differential pressure restraining line, primary Ioops temperature limiting line, the adjusting of primary Ioops pressurizer safety valve
It is worth curve, primary Ioops residual heat removal system cut-in temperature restraining line, upper pressure limit limits after residual heat removal system connection in primary Ioops
The primary Ioops temperature and pressure that line processed, primary Ioops Pressurizer surge line thermal stress restraining line, primary Ioops minimum temperature restraining line are constituted
Power run-limiting range.
In the above-mentioned one loop of nuclear power station abnormality tracing and monitoring method of the embodiment of the present invention, when the abnormality
When for fault condition, under the primary Ioops abnormality temperature and pressure run-limiting model include: by primary Ioops water it is full
The primary Ioops temperature constituted with curve, fault condition repair line, primary Ioops reduced pressure operation indication wire, primary Ioops reduced pressure operation restraining line
Degree and pressure run-limiting range, the fault condition repair line include: to forbid booster line, supercooling boundary limit value line, primary Ioops
Main pump restraining line.
In the above-mentioned one loop of nuclear power station abnormality tracing and monitoring method of the embodiment of the present invention, when the abnormality
For accident conditions and when the non-signal of P comes into force, temperature and pressure run-limiting model includes: by one under the primary Ioops abnormality
The saturation curve of water, the first operation lower limit restraining line, the first accident conditions repair restraining line, the first operation ceiling restriction in circuit
The primary Ioops temperature and pressure run-limiting range that line, primary Ioops Pressurizer surge line thermal stress restraining line are constituted；
When the abnormality is accident conditions and P signal comes into force, temperature and pressure under the primary Ioops abnormality
Run-limiting model includes: by the saturation curve of water, the second operation lower limit restraining line, the second accident conditions reparation limit in primary Ioops
The primary Ioops temperature and pressure operation of line, the second operation ceiling restriction line, back pressure force container thermal stress restraining line composition processed limits
Range processed.
On the other hand, the embodiment of the invention provides a kind of one loop of nuclear power station abnormality Tracking monitoring systems, comprising:
Module is constructed, for according to the operation characteristic and run-limiting item under preset one loop of nuclear power station abnormality
Part constructs temperature and pressure run-limiting model under primary Ioops abnormality；
Selecting module, for according to the primary Ioops main pump operating status of nuclear power station, the accident operating standard shape being carrying out
State and P signal state, to select corresponding primary Ioops temperature and pressure run-limiting model, the P signal is for influencing core
The trigger condition of power plant safety injecting systems；
Processing module, for obtaining the operating status of one loop of nuclear power station under abnormality, and according to the primary Ioops of selection
Temperature and pressure run-limiting model under abnormality adjusts the operation reserve of primary Ioops in real time, until smoothly recession is extremely pacified
Total state.
In the above-mentioned one loop of nuclear power station abnormality Tracking monitoring system of the embodiment of the present invention, the abnormality packet
It includes: losing the naturally circulated condition, fault condition and accident conditions of forced circulation function.
In the above-mentioned one loop of nuclear power station abnormality Tracking monitoring system of the embodiment of the present invention, when the abnormality
When for naturally circulated condition, temperature and pressure run-limiting model includes: by water in primary Ioops under the primary Ioops abnormality
Saturation curve, primary Ioops pressure low limit line, the high restraining line of primary Ioops pressure, primary Ioops primary side of steam generator differential pressure limit
Line processed, primary Ioops steam generator secondary side differential pressure restraining line, primary Ioops temperature limiting line, the adjusting of primary Ioops pressurizer safety valve
It is worth curve, primary Ioops residual heat removal system cut-in temperature restraining line, upper pressure limit limits after residual heat removal system connection in primary Ioops
The primary Ioops temperature and pressure that line processed, primary Ioops Pressurizer surge line thermal stress restraining line, primary Ioops minimum temperature restraining line are constituted
Power run-limiting range.
In the above-mentioned one loop of nuclear power station abnormality Tracking monitoring system of the embodiment of the present invention, when the abnormality
When for fault condition, under the primary Ioops abnormality temperature and pressure run-limiting model include: by primary Ioops water it is full
The primary Ioops temperature constituted with curve, fault condition repair line, primary Ioops reduced pressure operation indication wire, primary Ioops reduced pressure operation restraining line
Degree and pressure run-limiting range, the fault condition repair line include: to forbid booster line, supercooling boundary limit value line, primary Ioops
Main pump restraining line.
In the above-mentioned one loop of nuclear power station abnormality Tracking monitoring system of the embodiment of the present invention, when the abnormality
For accident conditions and when the non-signal of P comes into force, temperature and pressure run-limiting model includes: by one under the primary Ioops abnormality
The saturation curve of water, the first operation lower limit restraining line, the first accident conditions repair restraining line, the first operation ceiling restriction in circuit
The primary Ioops temperature and pressure run-limiting range that line, primary Ioops Pressurizer surge line thermal stress restraining line are constituted；
When the abnormality is accident conditions and P signal comes into force, temperature and pressure under the primary Ioops abnormality
Run-limiting model includes: by the saturation curve of water, the second operation lower limit restraining line, the second accident conditions reparation limit in primary Ioops
The primary Ioops temperature and pressure operation of line, the second operation ceiling restriction line, back pressure force container thermal stress restraining line composition processed limits
Range processed.
Technical solution provided in an embodiment of the present invention has the benefit that
By combining operation characteristic and run-limiting condition under one loop of nuclear power station abnormality, building primary Ioops are abnormal
Temperature and pressure run-limiting model under state, draws out the primary Ioops under naturally circulated condition, fault condition and accident conditions
Temperature and pressure run-limiting figure, it is automatic based on primary Ioops operating status under these run-limiting figures building failure and accident conditions
Tracking can assist operator during executing accident operating standard using the latter loop state automatic tracking method of accident
The convenient operating status for intuitively monitoring primary Ioops, tracks the evolutionary process and trend of primary Ioops state, is located at not in operating point
Suitable operation reserve is adjusted according to accident operating standard in time when in same region, primary Ioops state is made to be in monitoring always
Under, it smoothly drops back to safe condition.
Detailed description of the invention
To describe the technical solutions in the embodiments of the present invention more clearly, make required in being described below to embodiment
Attached drawing is briefly described, it should be apparent that, drawings in the following description are only some embodiments of the invention, for
For those of ordinary skill in the art, without creative efforts, it can also be obtained according to these attached drawings other
Attached drawing.
Fig. 1 is a kind of one loop of nuclear power station abnormality tracing and monitoring method flow diagram that the embodiment of the present invention one provides；
Fig. 2 is the primary Ioops temperature and pressure run-limiting under a kind of naturally circulated condition that the embodiment of the present invention one provides
Figure；
Fig. 3 is the primary Ioops temperature and pressure run-limiting figure under a kind of fault condition that the embodiment of the present invention one provides；
Primary Ioops temperature and pressure when Fig. 4 is a kind of P26 Pending The Entry Into Force of the offer of the embodiment of the present invention one under accident conditions
Run-limiting figure；
Fig. 5 is primary Ioops temperature and pressure when a kind of P26 that the embodiment of the present invention one provides has come into force under accident conditions
Run-limiting figure；
Fig. 6 is a kind of primary Ioops temperature and pressure run-limiting figure selection logic signal that the embodiment of the present invention one provides
Figure；
Fig. 7 is a kind of one loop of nuclear power station abnormality Tracking monitoring system structural representation provided by Embodiment 2 of the present invention
Figure.
Specific embodiment
To make the object, technical solutions and advantages of the present invention clearer, below in conjunction with attached drawing to embodiment party of the present invention
Formula is described in further detail.
Embodiment one
The embodiment of the invention provides a kind of one loop of nuclear power station abnormality tracing and monitoring methods, referring to Fig. 1, this method
May include:
Step S11, according to the operation characteristic and run-limiting condition under preset one loop of nuclear power station abnormality, building
Temperature and pressure run-limiting model under primary Ioops abnormality.
In the present embodiment, run-limiting condition refers to the various limitation requirements that should be abided by during nuclear power plant's operation, these limits
Condition processed be probably derived from unit safety in terms of requirement, important equipment operation, system operation limitation etc..Violate operation limit
Condition processed means that power plant may face the risk of safety, unexpected shutdown shutdown and equipment damage etc..Primary Ioops
Capital equipment includes: the equipment such as main pump, reactor core, pressure vessel, evaporator, voltage-stablizer.
In the present embodiment, the concept of primary Ioops temperature and pressure run-limiting figure can be extended under abnormality,
Form temperature and pressure run-limiting model under primary Ioops abnormality.
Specifically, abnormality may include: the naturally circulated condition for losing forced circulation function, fault condition and
Accident conditions.
In the present embodiment, Natural Circulation, refer to all reactor coolant pumps (main pump) circuit will because of steam generator and
The potential difference of reactor core display establishes Natural Circulation, and the situation of reactor core forced circulation forfeiture is stopped transport and caused in export.Fault condition covering
Some typical nuclear power plant's failures are as unavailable etc. in run out of steam or controlling system function caused by power supply, certain equipment fault.
Further, when abnormality is naturally circulated condition, temperature and pressure operation limit under primary Ioops abnormality
Simulation includes: by the saturation curve of water, primary Ioops pressure low limit line, the high restraining line of primary Ioops pressure, one time in primary Ioops
Road primary side of steam generator differential pressure restraining line, primary Ioops steam generator secondary side differential pressure restraining line, primary Ioops temperature limiting
Line, primary Ioops pressurizer safety valve setting valve curve, primary Ioops residual heat removal system cut-in temperature restraining line, waste heat in primary Ioops
Upper pressure limit restraining line, primary Ioops Pressurizer surge line thermal stress restraining line, primary Ioops minimum temperature limit after discharge system connection
The primary Ioops temperature and pressure run-limiting range that line processed is constituted.
In the present embodiment, when primary Ioops lose forced circulation (such as loss of off-site power causes all main pumps to be stopped transport),
The heat of reactor core will be exported mainly by Natural Circulation by steam generator, the primary Ioops temperature and pressure under accidental conditions
Run-limiting figure will be no longer applicable in, it is necessary to take into account primary Ioops temperature the characteristics of Natural Circulation under building naturally circulated condition and
Pressure run-limiting figure, to assist operator to track operating states of the units under naturally circulated condition.
It selects core exit coolant temperature maximum of T RIC max as representational primary Ioops temperature, selects peace
Primary Ioops pressure measurement channel P RCP loaded on main pipeline represents primary Ioops pressure.By taking certain compacted clay liners as an example, draw
Primary Ioops temperature and pressure run-limiting figure under its naturally circulated condition, as shown in Figure 2.To the explanation of each restraining line in figure
It is as follows:
A): the saturation curve of water in primary Ioops
B): right (low) restraining line of primary Ioops pressure
Relative saturation curve chooses certain supercooling allowance (such as taking 20 DEG C of allowance) as the determining right limit of primary Ioops pressure
The foundation of line processed, it is ensured that the error of Measurement channel not will lead to cooling boundary and lose.Under low pressure, since measurement error is excessive,
The supercooling boundary (20 DEG C) of selection can not guarantee that cooling boundary will not lose, and therefore, repair under low pressure to the curve
Just, it is ensured that supercooling boundary will not lose.
C): left (height) restraining line of primary Ioops pressure
The foundation that the restraining line determines is led to avoid the pressure-bearing thermal shock that reactor pressure vessel may be born after accident
The brittle fracture risk of cause (is lower than 140 DEG C as limited supercooling boundary, coolant degree of supercooling is more than that the value thinks primary Ioops extremely
Supercooling, there are brittle fracture risks for reactor pressure vessel).
D and E): primary Ioops steam generator one/secondary side differential pressure restraining line
Under naturally circulated condition, cold tube section temperature can be approximately considered and be approximately equal to steam generator secondary side coolant
Temperature, steam generator secondary side coolant is generally saturation state, and saturation temperature depends on the pressure of steam generator.
Under Natural Circulation state, the temperature difference of cold tube section and hot pipe section depends on afterheat heat output level, and afterheat heat output is horizontal
Related with the factors such as initial power, Shutdown time and burnup, therefore, the temperature difference is different under different conditions.But generally
In the case of the temperature difference do not exceed a certain limit value (such as 25 DEG C).
Here two steam generator one/secondary side differential pressure restraining lines are drawn out, hot pipe section/cold tube section temperature is corresponded respectively to
Difference is 0 DEG C and the situation of a certain limit value (such as 25 DEG C), and a region (region 2 in Fig. 2) delimited out in this two restraining lines, at this
In region, need to check the differential pressure of one/secondary side of steam generator lower than a certain limiting design value (such as 110bar).
F and G): primary Ioops temperature limiting line
Cold tube section temperature should be lower than the corresponding saturation temperature of steam generator safety valve setting value (such as steam generator safety
The set-pressure of valve is 89barG, and corresponding saturation temperature is 303 DEG C).Generally not in view of the temperature difference of hot pipe section and cold tube section
More than a certain limit value (such as 25 DEG C), there is also a upper limit (accordingly taking 303 DEG C+25 DEG C=328 DEG C) for core exit maximum temperature.
The two temperature limits limit region 3, and in region 3, operator should check boiler pressure lower than steam generator
Safety valve setting value, to take precautions against the risk of steam generator safety valve unlatching.
H): primary Ioops pressurizer safety valve setting valve curve
Pressurizer safety valve setting valve defines the maximum pressure of primary Ioops.It is general to install to typical PWR nuclear power plant
Have three-level setting valve different safety valve (e.g., certain nuclear power plant's three-level pressurizer safety valve setting valve takes 171barA respectively,
174barA, 177barA).
I): primary Ioops residual heat removal system cut-in temperature restraining line
The foundation that the restraining line determines is the permission cut-in temperature (such as 120 DEG C) of residual heat removal system.
J): upper pressure limit restraining line after residual heat removal system connection in primary Ioops
The foundation that the restraining line determines is permitted maximum pressure (such as 31barg) after residual heat removal system connection.
K): primary Ioops Pressurizer surge line thermal stress restraining line
The temperature difference at the Pressurizer surge line both ends that the foundation that the restraining line determines allows for design, on limitation fluctuation pipeline
Thermal stress (if limitation Surge line piping temperature difference between the two ends are no more than 180 DEG C).The curve is used as the lower limit in region 1 simultaneously, in region 1
Interior, operator should check that voltage-stablizer is water entity state.
L): primary Ioops minimum temperature restraining line
The restraining line determine foundation be under low temperature boron crystallization risk (as select 10 DEG C as primary Ioops at a temperature of
Limit, the risk of boron crystallization when preventing boron concentration to be higher than 2000ppm).
Further, when abnormality is fault condition, temperature and pressure run-limiting mould under primary Ioops abnormality
Type includes: by the saturation curve of water, fault condition repair line, primary Ioops reduced pressure operation indication wire, primary Ioops decompression in primary Ioops
The primary Ioops temperature and pressure run-limiting range that restraining line is constituted is operated, fault condition repair line includes: to forbid booster line, mistake
Cold boundary limit value line, primary Ioops main pump restraining line.
In the present embodiment, fault condition cover some typical nuclear power plant's failures such as run out of steam or control power supply, certain
System function caused by equipment fault is unavailable etc..Under fault condition, Core cooling state does not deteriorate, and does not need ad hoc peace
Full facility investment.The target of fault condition operation is to stablize set state, the equipment for repairing power supply or failure as early as possible, to connect as far as possible
The mode closely operated normally controls unit, and unit is enable to restore to operate normally as early as possible, or guidance operator make unit drop back to
Recession mode predetermined avoids the deterioration of set state and then is directed to accident conditions.
It selects core exit coolant temperature maximum of T RIC max as representational primary Ioops temperature, selects peace
Primary Ioops pressure measurement channel P RCP loaded on hot pipe section represents primary Ioops pressure.By taking certain compacted clay liners as an example, draw
Primary Ioops temperature and pressure run-limiting figure under its fault condition, as shown in Figure 3.Such as to the explanation of each restraining line in figure
Under:
A): the saturation curve of primary Ioops water
B): fault condition repairs restraining line
Fault condition repairs the foundation that restraining line determines are as follows: as long as operating pressure keeps above, not may require that and holding
Row restores the relevant operation of degree of supercooling.Fault condition repairs restraining line and consists of the following components:
Forbid boosting on limit value (restraining line top): being more than this pressure limit, primary Ioops boosting would be impossible to make to run shape
Within the scope of state point is limited back to intermediate restraining line and left restraining line；
Be subcooled boundary limit value (in the middle part of restraining line): the limit value is according to the primary Ioops temperature and pressure fortune under accidental conditions
The right boundary line of row limitation figure determines, and considers certain allowance (such as accidental conditions primary Ioops temperature and pressure operation limit
Drawing the right boundary line takes 40 DEG C of degree of supercooling, considers 10 DEG C of allowance, it is degree of supercooling that fault condition, which repairs the foundation that restraining line determines,
50℃)；
Primary Ioops main pump restraining line (restraining line lower part): needed for the foundation that the part restraining line determines is ensures that main pump is run
The minimum pressure of the specified conditions of satisfaction, including the restraining line main pump NPSH, main pump operation requires (such as 24barA).
C): primary Ioops reduced pressure operation indication wire
The purpose of the restraining line be prompt operator pressure reduction will at the end of not take excessively fierce decompression
Operation, to avoid accident operating conditions are eventually led to.The restraining line is repaired restraining line according to fault condition and is determined, and considers one
Fixed allowance (allowance as considered 10 DEG C, the foundation that intermediate restraining line determines are 60 DEG C of degree of supercooling).
D): primary Ioops reduced pressure operation restraining line
The purpose of the restraining line is the restrictive condition for providing reduced pressure operation.It is to allow to be depressured as early as possible and while keeping enough
Saturation nargin (to avoid be directed to accident conditions operation) compromise.The restraining line is suitable according to Pressurizer surge line stress analysis
The peak of the Pressurizer surge line temperature difference between the two ends provided in II class transient analysis determines (such as 110 DEG C).
Further, when abnormality is accident conditions and the non-signal of P comes into force, temperature and pressure under primary Ioops abnormality
Power run-limiting model includes: by the saturation curve of water, the first operation lower limit restraining line, the first accident conditions reparation in primary Ioops
The primary Ioops temperature and pressure that restraining line, the first operation ceiling restriction line, primary Ioops Pressurizer surge line thermal stress restraining line are constituted
Power run-limiting range；
When abnormality is accident conditions and P signal comes into force, temperature and pressure run-limiting under primary Ioops abnormality
Model includes: to repair restraining line, the by the saturation curve of water in primary Ioops, the second operation lower limit restraining line, the second accident conditions
The primary Ioops temperature and pressure run-limiting range that two operation ceiling restriction lines, a back pressure force container thermal stress restraining line are constituted.
In the present embodiment, the primary Ioops temperature and pressure run-limiting figure under accident conditions is primarily adapted for use in Core cooling
The situation that state does not deteriorate is joined with assisting operator to track primary Ioops to cold shutdown transition period in execution accident operating standard
Several variation tendencies should avoid the triggering of the engineered safeguards features such as safety injection system as far as possible in the process.
In view of environment may deteriorate in containment under accident conditions, pressure parameter takes primary Ioops absolute pressure: P
HL (the primary Ioops relative pressure that hot pipe section measures)+P CON (containment pressure).Select core exit coolant temperature maximum value
T RIC max is as representational primary Ioops temperature.
By taking certain compacted clay liners as an example, the primary Ioops temperature allowed under signal P26 Pending The Entry Into Force and active states is drawn
(after allowing signal P26 to come into force, the trigger condition of safety injection signal is saturated abundant by hot pipe section coolant with pressure run-limiting figure
It is low that degree forfeiture switches to hot pipe section loop water level).Primary Ioops temperature and pressure run-limiting when P26 Pending The Entry Into Force under accident conditions
Figure is as shown in Figure 4.Each restraining line in figure is described as follows:
A): the saturation curve of primary Ioops water
B): the first operation lower limit restraining line
Operation lower limit restraining line is made of following several parts:
High temperature and pressure part: the foundation determined is that avoid hot pipe section from occurring while to primary Ioops reduction of blood pressure in high-speed too low
It is saturated nargin and triggers safety injection signal due to hot pipe section coolant saturation nargin is lost.Therefore, which is based on protecting
The threshold value that protecting system triggers safety injection signal determines；
Low-pressure low-temperature part: determine foundation with for guarantee main pump operation and maintenance operating pressure interval limit (such as
27bara)。
C): accident conditions repair restraining line
Accident conditions are repaired restraining line and are made of following several parts:
High pressure-temperature part: this is based partially on the operation lower limit restraining line under high-temperature and high-pressure conditions, and takes certain allowance
(such as taking 10 DEG C of allowance).
Low-pressure low-temperature part: this is based partially on fault condition reparation restraining line and determines, and considers that certain allowance (such as takes
The allowance of 4bar), to allow to execute the operation of the degree of supercooling reparation under fault condition there are enough running spaces, in failure
Without being directed towards accident conditions after successfully being repaired under operating condition.
D) the first operation ceiling restriction line
Operation ceiling restriction line is made of following several parts:
High pressure-temperature part: the restrictive curve is determined based on the operation lower limit restrictive curve under the conditions of, and is subject to certain
Allowance (such as taking 45 DEG C of allowance).
Low-pressure low-temperature part: the operating pressure section upper limit maintained according to being to guarantee main pump operation determined is (such as
29bara)。
E): primary Ioops Pressurizer surge line thermal stress restraining line
The temperature difference at the Pressurizer surge line both ends that the foundation that the restraining line determines allows for design, on limitation fluctuation pipeline
Thermal stress (if limitation Surge line piping temperature difference between the two ends are no more than 180 DEG C).
Primary Ioops temperature and pressure run-limiting figure when P26 comes into force under accident conditions, accident conditions when being P26 Pending The Entry Into Force
Under primary Ioops temperature and pressure run-limiting figure extension, as shown in Figure 5.Each restraining line in figure is described as follows:
A): the saturation curve of primary Ioops water
B): the second operation lower limit restraining line
Operation lower limit restraining line is made of following several parts:
High pressure-temperature part: the low-pressure low-temperature part for running lower limit restraining line when P26 Pending The Entry Into Force is accepted in the part, until
Reach low temperature (such as 55 DEG C) and decompression state.
Low-temp low-pressure part: this part is provided by temperature (such as 55 DEG C) condition of the cold shutdown state of final goal.
C): the second accident conditions repair restraining line
Accident conditions are repaired restraining line and are made of following several parts:
High pressure-temperature part: the restraining line is operation lower limit restraining line high temperature and pressure part and the enough saturation nargin of holding
Compromise.In a low voltage state, since measurement error is larger, biggish allowance is taken (such as to take 20 DEG C abundant relative to saturation curve
Amount).
Low-pressure low-temperature part: temperature is lower than 100 DEG C under atmospheric pressure, it can be ensured that is not saturated, considers certain allowance
(such as taking 20 DEG C of allowance), the restraining line are vertical line (80 DEG C).
D) the second operation ceiling restriction line
Operation ceiling restriction line is made of following several parts:
High pressure-temperature part: the restrictive curve is determined based on operation lower limit restraining line high temperature and pressure part, and is considered certain
Allowance (such as taking 35 DEG C of allowance).
Low-temp low-pressure part: in the region, the pressure upper limit of target is based primarily upon following factor and determines: it should be higher than that operation
The pressure that lower limit restraining line limits, while the pressure is also answered sufficiently low so that primary Ioops can consider almost pressure release.
E): primary Ioops pressure vessel thermal stress restraining line
The foundation that the restraining line determines is led to avoid the pressure-bearing thermal shock that reactor pressure vessel may be born after accident
The brittle fracture risk (being lower than 140 DEG C as limited degree of supercooling) of cause.
In the present embodiment, by choosing reasonable monitoring parameters, failure or accident work are determined based on these monitoring parameters
One time under failure and accident conditions is drawn respectively for the consistency for guaranteeing and operating normally in run-limiting boundary under condition
Road temperature and pressure run-limiting figure.It can remember automatically on a loop temperature and pressure run-limiting figure under failure or accident conditions
The state point of each moment primary Ioops is recorded and shows, in order to assist operator easily to supervise during executing accident operating standard
Control the operating status of primary Ioops, track the Evolution Paths and trend of primary Ioops parameter, with operating point beyond primary Ioops temperature and
Change operation reserve when the running boundary that pressure run-limiting figure limits in time, reduction as far as possible runs system and equipment unfavorable
It influences, unit is enable steadily to drop back in the range of primary Ioops temperature and pressure run-limiting figure limits to safe condition.
Step S12, according to the primary Ioops main pump operating status of nuclear power station, the accident operating standard state being carrying out, with
And P signal state, to select corresponding primary Ioops temperature and pressure run-limiting model, P signal (P26 letter i.e. mentioned above
Number) for influencing the trigger condition of nuclear plant safety injecting systems.
In the present embodiment, accident operating standard is the file write in the form of sequential instructions, in fault condition and
It guides operator to control unit under accident conditions, stablizes merger after unit in safe shutdown state.Not due to operational objective
Together, accident operating standard can be divided under fault condition accident operating standard (target be stablize unit or unit made to drop back, therefore
Barrier repair after restore as early as possible unit operation) and accident conditions under accident operating standard (target be recovery and maintain reactor core long-term
It is cooling, avoid core meltdown).
In the present embodiment, according to the choosing of the conditions such as main pump operating status, regulation state and P signal (i.e. P26 signal) state
Select the primary Ioops temperature and pressure run-limiting figure being applicable under current state.Its logic is as shown in fig. 6, specific explanations are as follows:
If failure or accident conditions accident operating standard are executing, it is desirable that stablize in current state and main pump has been stopped transport,
Then select naturally circulated condition primary Ioops temperature and pressure run-limiting figure；
If fault condition accident operating standard is executing, not aspire for stability in current state (recession), or to aspire for stability
In current state but main pump is being run, and selects fault condition primary Ioops temperature and pressure run-limiting figure；
If accident conditions accident operating standard is executing, not aspire for stability in current state (recession), or to aspire for stability
In current state but main pump is being run, then selects corresponding accident conditions primary Ioops temperature and pressure whether coming into force according to P26 signal
Power run-limiting figure；
If fault condition and accident conditions accident operating standard are not executing, directly exit.
Step S13 obtains the operating status of one loop of nuclear power station under abnormality, and according to the primary Ioops exception shape of selection
Temperature and pressure run-limiting model under state, adjusts the operation reserve of primary Ioops in real time, until smoothly dropping back to safe condition.
In the present embodiment, after main acquisition description failure or accident primary Ioops temperature needed for primary Ioops operating status and
Pressure parameter, mainly include primary Ioops pressure P RCP (gauge pressure), hot pipe section pressure P HL (gauge pressure), containment pressure P CON,
Core exit coolant temperature T RIC etc..In practical applications, temperature and pressure parameter polygamy is equipped with the Measurement channel of redundancy
(typical nuclear power plant is generally 4 column redundancies), signal processing module to the collected pressure and temperature signal of signal acquisition module into
Row processing, including identifying and rejecting invalid Measurement channel etc..
General nuclear power plant arranges about 20 thermocouples in core exit to measure point of core exit coolant temperature T RIC
Cloth situation, signal processing module calculate the maximum of T RIC of core exit coolant temperature according to these thermocouple measurement signals
max.Signal processing module is performed simultaneously simple calculations, as calculated accident conditions primary Ioops temperature and pressure run-limiting figure institute
The primary Ioops absolute pressure P HL+PCON needed.In order to avoid the influence of the factors such as possible instrument drift table, signal processing module choosing
The Second Largest Value of redundant channel is selected as the parameter for representing primary Ioops virtual condition.
In the present embodiment, the one loop of nuclear power station abnormality tracing and monitoring method, first combination failure operating condition and thing
Therefore the characteristics of unit is run under operating condition, various run-limiting conditions are indicated in the form of temperature and pressure run-limiting figure, are drawn
The primary Ioops temperature and pressure run-limiting figure under naturally circulated condition, fault condition and accident conditions is produced, based on these fortune
Primary Ioops operating status automatic tracking method under row limitation figure building failure and accident conditions.Certainly using the latter loop state of accident
Motion tracking method can assist operator's convenient operating status for intuitively monitoring primary Ioops during executing accident operating standard,
The evolutionary process and trend for tracking primary Ioops state, when operating point is located in different regions in time according to accident operating standard
Suitable operation reserve is adjusted, is in primary Ioops state under monitoring always, is smoothly dropped back to safe condition.
The embodiment of the present invention is by combining operation characteristic and run-limiting condition under one loop of nuclear power station abnormality, structure
Temperature and pressure run-limiting model under primary Ioops abnormality is built, naturally circulated condition, fault condition and accident work are drawn out
Primary Ioops temperature and pressure run-limiting figure under condition, based on primary Ioops under these run-limiting figures building failure and accident conditions
Operating status automatic tracking method can assist operator in execution accident using the latter loop state automatic tracking method of accident
The convenient operating status for intuitively monitoring primary Ioops, tracks the evolutionary process and trend of primary Ioops state during operating standard,
Suitable operation reserve is adjusted according to accident operating standard in time when operating point is located in different regions, primary Ioops state is made to begin
Eventually under monitoring, smoothly drop back to safe condition.
Embodiment two
The embodiment of the invention provides a kind of one loop of nuclear power station abnormality Tracking monitoring systems, perform embodiment one
The method, referring to Fig. 7, which may include: building module 100, selecting module 200, processing module 300.
Module 100 is constructed, for according to the operation characteristic and run-limiting under preset one loop of nuclear power station abnormality
Condition constructs temperature and pressure run-limiting model under primary Ioops abnormality.
In the present embodiment, run-limiting condition refers to the various limitation requirements that should be abided by during nuclear power plant's operation, these limits
Condition processed be probably derived from unit safety in terms of requirement, important equipment operation, system operation limitation etc..Violate operation limit
Condition processed means that power plant may face the risk of safety, unexpected shutdown shutdown and equipment damage etc..Primary Ioops
Capital equipment includes: the equipment such as main pump, reactor core, pressure vessel, evaporator, voltage-stablizer.
In the present embodiment, the concept of primary Ioops temperature and pressure run-limiting figure can be extended under abnormality,
Form temperature and pressure run-limiting model under primary Ioops abnormality.
Selecting module 200, for according to the primary Ioops main pump operating status of nuclear power station, the accident operating standard being carrying out
State and P signal state, to select corresponding primary Ioops temperature and pressure run-limiting model, P signal (is previously mentioned
P26 signal) for influencing the trigger conditions of nuclear plant safety injecting systems.
In the present embodiment, accident operating standard is the file write in the form of sequential instructions, in fault condition and
It guides operator to control unit under accident conditions, stablizes merger after unit in safe shutdown state.Not due to operational objective
Together, accident operating standard can be divided under fault condition accident operating standard (target be stablize unit or unit made to drop back, therefore
Barrier repair after restore as early as possible unit operation) and accident conditions under accident operating standard (target be recovery and maintain reactor core long-term
It is cooling, avoid core meltdown).
In the present embodiment, according to the choosing of the conditions such as main pump operating status, regulation state and P signal (i.e. P26 signal) state
Select the primary Ioops temperature and pressure run-limiting figure being applicable under current state.Its logic is as follows:
If failure or accident conditions accident operating standard are executing, it is desirable that stablize in current state and main pump has been stopped transport,
Then select naturally circulated condition primary Ioops temperature and pressure run-limiting figure；
If fault condition accident operating standard is executing, not aspire for stability in current state (recession), or to aspire for stability
In current state but main pump is being run, and selects fault condition primary Ioops temperature and pressure run-limiting figure；
If accident conditions accident operating standard is executing, not aspire for stability in current state (recession), or to aspire for stability
In current state but main pump is being run, then selects corresponding accident conditions primary Ioops temperature and pressure whether coming into force according to P26 signal
Power run-limiting figure；
If fault condition and accident conditions accident operating standard are not executing, directly exit.
Processing module 300, for obtaining the operating status of one loop of nuclear power station under abnormality, and according to one time of selection
Temperature and pressure run-limiting model under the abnormality of road, in real time adjust primary Ioops operation reserve, until smoothly drop back to
Safe condition.
In the present embodiment, after main acquisition description failure or accident primary Ioops temperature needed for primary Ioops operating status and
Pressure parameter, mainly include primary Ioops pressure P RCP (gauge pressure), hot pipe section pressure P HL (gauge pressure), containment pressure P CON,
Core exit coolant temperature T RIC etc..In practical applications, temperature and pressure parameter polygamy is equipped with the Measurement channel of redundancy
(typical nuclear power plant is generally 4 column redundancies), signal processing module to the collected pressure and temperature signal of signal acquisition module into
Row processing, including identifying and rejecting invalid Measurement channel etc..
General nuclear power plant arranges about 20 thermocouples in core exit to measure point of core exit coolant temperature T RIC
Cloth situation, signal processing module calculate the maximum of T RIC of core exit coolant temperature according to these thermocouple measurement signals
max.Signal processing module is performed simultaneously simple calculations, as calculated accident conditions primary Ioops temperature and pressure run-limiting figure institute
The primary Ioops absolute pressure P HL+PCON needed.In order to avoid the influence of the factors such as possible instrument drift table, signal processing module choosing
The Second Largest Value of redundant channel is selected as the parameter for representing primary Ioops virtual condition.
In the present embodiment, the one loop of nuclear power station abnormality tracing and monitoring method, first combination failure operating condition and thing
Therefore the characteristics of unit is run under operating condition, various run-limiting conditions are indicated in the form of temperature and pressure run-limiting figure, are drawn
The primary Ioops temperature and pressure run-limiting figure under naturally circulated condition, fault condition and accident conditions is produced, based on these fortune
Primary Ioops operating status automatic tracking method under row limitation figure building failure and accident conditions.Certainly using the latter loop state of accident
Motion tracking method can assist operator's convenient operating status for intuitively monitoring primary Ioops during executing accident operating standard,
The evolutionary process and trend for tracking primary Ioops state, when operating point is located in different regions in time according to accident operating standard
Suitable operation reserve is adjusted, is in primary Ioops state under monitoring always, is smoothly dropped back to safe condition.
Specifically, abnormality may include: the naturally circulated condition for losing forced circulation function, fault condition and
Accident conditions.
In the present embodiment, Natural Circulation, refer to all reactor coolant pumps (main pump) circuit will because of steam generator and
The potential difference of reactor core display establishes Natural Circulation, and the situation of reactor core forced circulation forfeiture is stopped transport and caused in export.Fault condition covering
Some typical nuclear power plant's failures are as unavailable etc. in run out of steam or controlling system function caused by power supply, certain equipment fault.
Further, when abnormality is naturally circulated condition, temperature and pressure operation limit under primary Ioops abnormality
Simulation includes: by the saturation curve of water, primary Ioops pressure low limit line, the high restraining line of primary Ioops pressure, one time in primary Ioops
Road primary side of steam generator differential pressure restraining line, primary Ioops steam generator secondary side differential pressure restraining line, primary Ioops temperature limiting
Line, primary Ioops pressurizer safety valve setting valve curve, primary Ioops residual heat removal system cut-in temperature restraining line, waste heat in primary Ioops
Upper pressure limit restraining line, primary Ioops Pressurizer surge line thermal stress restraining line, primary Ioops minimum temperature limit after discharge system connection
The primary Ioops temperature and pressure run-limiting range that line processed is constituted.
In the present embodiment, when primary Ioops lose forced circulation (such as loss of off-site power causes all main pumps to be stopped transport),
The heat of reactor core will be exported mainly by Natural Circulation by steam generator, the primary Ioops temperature and pressure under accidental conditions
Run-limiting figure will be no longer applicable in, it is necessary to take into account primary Ioops temperature the characteristics of Natural Circulation under building naturally circulated condition and
Pressure run-limiting figure, to assist operator to track operating states of the units under naturally circulated condition.
It selects core exit coolant temperature maximum of T RIC max as representational primary Ioops temperature, selects peace
Primary Ioops pressure measurement channel P RCP loaded on main pipeline represents primary Ioops pressure.By taking certain compacted clay liners as an example, draw
Primary Ioops temperature and pressure run-limiting figure under its naturally circulated condition, as shown in Figure 2.To the explanation of each restraining line in figure
It is as follows:
A): the saturation curve of water in primary Ioops
B): right (low) restraining line of primary Ioops pressure
Relative saturation curve chooses certain supercooling allowance (such as taking 20 DEG C of allowance) as the determining right limit of primary Ioops pressure
The foundation of line processed, it is ensured that the error of Measurement channel not will lead to cooling boundary and lose.Under low pressure, since measurement error is excessive,
The supercooling boundary (20 DEG C) of selection can not guarantee that cooling boundary will not lose, and therefore, repair under low pressure to the curve
Just, it is ensured that supercooling boundary will not lose.
C): left (height) restraining line of primary Ioops pressure
The foundation that the restraining line determines is led to avoid the pressure-bearing thermal shock that reactor pressure vessel may be born after accident
The brittle fracture risk of cause (is lower than 140 DEG C as limited supercooling boundary, coolant degree of supercooling is more than that the value thinks primary Ioops extremely
Supercooling, there are brittle fracture risks for reactor pressure vessel).
D and E): primary Ioops steam generator one/secondary side differential pressure restraining line
Under naturally circulated condition, cold tube section temperature can be approximately considered and be approximately equal to steam generator secondary side coolant
Temperature, steam generator secondary side coolant is generally saturation state, and saturation temperature depends on the pressure of steam generator.
Under Natural Circulation state, the temperature difference of cold tube section and hot pipe section depends on afterheat heat output level, and afterheat heat output is horizontal
Related with the factors such as initial power, Shutdown time and burnup, therefore, the temperature difference is different under different conditions.But generally
In the case of the temperature difference do not exceed a certain limit value (such as 25 DEG C).
Here two steam generator one/secondary side differential pressure restraining lines are drawn out, hot pipe section/cold tube section temperature is corresponded respectively to
Difference is 0 DEG C and the situation of a certain limit value (such as 25 DEG C), and a region (region 2 in Fig. 2) delimited out in this two restraining lines, at this
In region, need to check the differential pressure of one/secondary side of steam generator lower than a certain limiting design value (such as 110bar).
F and G): primary Ioops temperature limiting line
Cold tube section temperature should be lower than the corresponding saturation temperature of steam generator safety valve setting value (such as steam generator safety
The set-pressure of valve is 89barG, and corresponding saturation temperature is 303 DEG C).Generally not in view of the temperature difference of hot pipe section and cold tube section
More than a certain limit value (such as 25 DEG C), there is also a upper limit (accordingly taking 303 DEG C+25 DEG C=328 DEG C) for core exit maximum temperature.
The two temperature limits limit region 3, and in region 3, operator should check boiler pressure lower than steam generator
Safety valve setting value, to take precautions against the risk of steam generator safety valve unlatching.
H): primary Ioops pressurizer safety valve setting valve curve
Pressurizer safety valve setting valve defines the maximum pressure of primary Ioops.It is general to install to typical PWR nuclear power plant
Have three-level setting valve different safety valve (e.g., certain nuclear power plant's three-level pressurizer safety valve setting valve takes 171barA respectively,
174barA, 177barA).
I): primary Ioops residual heat removal system cut-in temperature restraining line
The foundation that the restraining line determines is the permission cut-in temperature (such as 120 DEG C) of residual heat removal system.
J): upper pressure limit restraining line after residual heat removal system connection in primary Ioops
The foundation that the restraining line determines is permitted maximum pressure (such as 31barg) after residual heat removal system connection.
K): primary Ioops Pressurizer surge line thermal stress restraining line
The temperature difference at the Pressurizer surge line both ends that the foundation that the restraining line determines allows for design, on limitation fluctuation pipeline
Thermal stress (if limitation Surge line piping temperature difference between the two ends are no more than 180 DEG C).The curve is used as the lower limit in region 1 simultaneously, in region 1
Interior, operator should check that voltage-stablizer is water entity state.
L): primary Ioops minimum temperature restraining line
The restraining line determine foundation be under low temperature boron crystallization risk (as select 10 DEG C as primary Ioops at a temperature of
Limit, the risk of boron crystallization when preventing boron concentration to be higher than 2000ppm).
Further, when abnormality is fault condition, temperature and pressure run-limiting mould under primary Ioops abnormality
Type includes: by the saturation curve of water, fault condition repair line, primary Ioops reduced pressure operation indication wire, primary Ioops decompression in primary Ioops
The primary Ioops temperature and pressure run-limiting range that restraining line is constituted is operated, fault condition repair line includes: to forbid booster line, mistake
Cold boundary limit value line, primary Ioops main pump restraining line.
In the present embodiment, fault condition cover some typical nuclear power plant's failures such as run out of steam or control power supply, certain
System function caused by equipment fault is unavailable etc..Under fault condition, Core cooling state does not deteriorate, and does not need ad hoc peace
Full facility investment.The target of fault condition operation is to stablize set state, the equipment for repairing power supply or failure as early as possible, to connect as far as possible
The mode closely operated normally controls unit, and unit is enable to restore to operate normally as early as possible, or guidance operator make unit drop back to
Recession mode predetermined avoids the deterioration of set state and then is directed to accident conditions.
It selects core exit coolant temperature maximum of T RIC max as representational primary Ioops temperature, selects peace
Primary Ioops pressure measurement channel P RCP loaded on hot pipe section represents primary Ioops pressure.By taking certain compacted clay liners as an example, draw
Primary Ioops temperature and pressure run-limiting figure under its fault condition, as shown in Figure 3.Such as to the explanation of each restraining line in figure
Under:
A): the saturation curve of primary Ioops water
B): fault condition repairs restraining line
Fault condition repairs the foundation that restraining line determines are as follows: as long as operating pressure keeps above, not may require that and holding
Row restores the relevant operation of degree of supercooling.Fault condition repairs restraining line and consists of the following components:
Forbid boosting on limit value (restraining line top): being more than this pressure limit, primary Ioops boosting would be impossible to make to run shape
Within the scope of state point is limited back to intermediate restraining line and left restraining line；
Be subcooled boundary limit value (in the middle part of restraining line): the limit value is according to the primary Ioops temperature and pressure fortune under accidental conditions
The right boundary line of row limitation figure determines, and considers certain allowance (such as accidental conditions primary Ioops temperature and pressure operation limit
Drawing the right boundary line takes 40 DEG C of degree of supercooling, considers 10 DEG C of allowance, it is degree of supercooling that fault condition, which repairs the foundation that restraining line determines,
50℃)；
Primary Ioops main pump restraining line (restraining line lower part): needed for the foundation that the part restraining line determines is ensures that main pump is run
The minimum pressure of the specified conditions of satisfaction, including the restraining line main pump NPSH, main pump operation requires (such as 24barA).
C): primary Ioops reduced pressure operation indication wire
The purpose of the restraining line be prompt operator pressure reduction will at the end of not take excessively fierce decompression
Operation, to avoid accident operating conditions are eventually led to.The restraining line is repaired restraining line according to fault condition and is determined, and considers one
Fixed allowance (allowance as considered 10 DEG C, the foundation that intermediate restraining line determines are 60 DEG C of degree of supercooling).
D): primary Ioops reduced pressure operation restraining line
The purpose of the restraining line is the restrictive condition for providing reduced pressure operation.It is to allow to be depressured as early as possible and while keeping enough
Saturation nargin (to avoid be directed to accident conditions operation) compromise.The restraining line is suitable according to Pressurizer surge line stress analysis
The peak of the Pressurizer surge line temperature difference between the two ends provided in II class transient analysis determines (such as 110 DEG C).
Further, when abnormality is accident conditions and the non-signal of P comes into force, temperature and pressure under primary Ioops abnormality
Power run-limiting model includes: by the saturation curve of water, the first operation lower limit restraining line, the first accident conditions reparation in primary Ioops
The primary Ioops temperature and pressure that restraining line, the first operation ceiling restriction line, primary Ioops Pressurizer surge line thermal stress restraining line are constituted
Power run-limiting range；
When abnormality is accident conditions and P signal comes into force, temperature and pressure run-limiting under primary Ioops abnormality
Model includes: to repair restraining line, the by the saturation curve of water in primary Ioops, the second operation lower limit restraining line, the second accident conditions
The primary Ioops temperature and pressure run-limiting range that two operation ceiling restriction lines, a back pressure force container thermal stress restraining line are constituted.
In the present embodiment, the primary Ioops temperature and pressure run-limiting figure under accident conditions is primarily adapted for use in Core cooling
The situation that state does not deteriorate is joined with assisting operator to track primary Ioops to cold shutdown transition period in execution accident operating standard
Several variation tendencies should avoid the triggering of the engineered safeguards features such as safety injection system as far as possible in the process.
In view of environment may deteriorate in containment under accident conditions, pressure parameter takes primary Ioops absolute pressure: P
HL (the primary Ioops relative pressure that hot pipe section measures)+P CON (containment pressure).Select core exit coolant temperature maximum value
T RIC max is as representational primary Ioops temperature.
By taking certain compacted clay liners as an example, the primary Ioops temperature allowed under signal P26 Pending The Entry Into Force and active states is drawn
(after allowing signal P26 to come into force, the trigger condition of safety injection signal is saturated abundant by hot pipe section coolant with pressure run-limiting figure
It is low that degree forfeiture switches to hot pipe section loop water level).Primary Ioops temperature and pressure run-limiting when P26 Pending The Entry Into Force under accident conditions
Figure is as shown in Figure 4.Each restraining line in figure is described as follows:
A): the saturation curve of primary Ioops water
B): the first operation lower limit restraining line
Operation lower limit restraining line is made of following several parts:
High temperature and pressure part: the foundation determined is that avoid hot pipe section from occurring while to primary Ioops reduction of blood pressure in high-speed too low
It is saturated nargin and triggers safety injection signal due to hot pipe section coolant saturation nargin is lost.Therefore, which is based on protecting
The threshold value that protecting system triggers safety injection signal determines；
Low-pressure low-temperature part: determine foundation with for guarantee main pump operation and maintenance operating pressure interval limit (such as
27bara)。
C): accident conditions repair restraining line
Accident conditions are repaired restraining line and are made of following several parts:
High pressure-temperature part: this is based partially on the operation lower limit restraining line under high-temperature and high-pressure conditions, and takes certain allowance
(such as taking 10 DEG C of allowance).
Low-pressure low-temperature part: this is based partially on fault condition reparation restraining line and determines, and considers that certain allowance (such as takes
The allowance of 4bar), to allow to execute the operation of the degree of supercooling reparation under fault condition there are enough running spaces, in failure
Without being directed towards accident conditions after successfully being repaired under operating condition.
D) the first operation ceiling restriction line
Operation ceiling restriction line is made of following several parts:
High pressure-temperature part: the restrictive curve is determined based on the operation lower limit restrictive curve under the conditions of, and is subject to certain
Allowance (such as taking 45 DEG C of allowance).
Low-pressure low-temperature part: the operating pressure section upper limit maintained according to being to guarantee main pump operation determined is (such as
29bara)。
E): primary Ioops Pressurizer surge line thermal stress restraining line
The temperature difference at the Pressurizer surge line both ends that the foundation that the restraining line determines allows for design, on limitation fluctuation pipeline
Thermal stress (if limitation Surge line piping temperature difference between the two ends are no more than 180 DEG C).
Primary Ioops temperature and pressure run-limiting figure when P26 comes into force under accident conditions, accident conditions when being P26 Pending The Entry Into Force
Under primary Ioops temperature and pressure run-limiting figure extension, as shown in Figure 5.Each restraining line in figure is described as follows:
A): the saturation curve of primary Ioops water
B): the second operation lower limit restraining line
Operation lower limit restraining line is made of following several parts:
High pressure-temperature part: the low-pressure low-temperature part for running lower limit restraining line when P26 Pending The Entry Into Force is accepted in the part, until
Reach low temperature (such as 55 DEG C) and decompression state.
Low-temp low-pressure part: this part is provided by temperature (such as 55 DEG C) condition of the cold shutdown state of final goal.
C): the second accident conditions repair restraining line
Accident conditions are repaired restraining line and are made of following several parts:
High pressure-temperature part: the restraining line is operation lower limit restraining line high temperature and pressure part and the enough saturation nargin of holding
Compromise.In a low voltage state, since measurement error is larger, biggish allowance is taken (such as to take 20 DEG C abundant relative to saturation curve
Amount).
Low-pressure low-temperature part: temperature is lower than 100 DEG C under atmospheric pressure, it can be ensured that is not saturated, considers certain allowance
(such as taking 20 DEG C of allowance), the restraining line are vertical line (80 DEG C).
D) the second operation ceiling restriction line
Operation ceiling restriction line is made of following several parts:
High pressure-temperature part: the restrictive curve is determined based on operation lower limit restraining line high temperature and pressure part, and is considered certain
Allowance (such as taking 35 DEG C of allowance).
Low-temp low-pressure part: in the region, the pressure upper limit of target is based primarily upon following factor and determines: it should be higher than that operation
The pressure that lower limit restraining line limits, while the pressure is also answered sufficiently low so that primary Ioops can consider almost pressure release.
E): primary Ioops pressure vessel thermal stress restraining line
The foundation that the restraining line determines is led to avoid the pressure-bearing thermal shock that reactor pressure vessel may be born after accident
The brittle fracture risk (being lower than 140 DEG C as limited degree of supercooling) of cause.
In the present embodiment, by choosing reasonable monitoring parameters, failure or accident work are determined based on these monitoring parameters
One time under failure and accident conditions is drawn respectively for the consistency for guaranteeing and operating normally in run-limiting boundary under condition
Road temperature and pressure run-limiting figure.It can remember automatically on a loop temperature and pressure run-limiting figure under failure or accident conditions
The state point of each moment primary Ioops is recorded and shows, in order to assist operator easily to supervise during executing accident operating standard
Control the operating status of primary Ioops, track the Evolution Paths and trend of primary Ioops parameter, with operating point beyond primary Ioops temperature and
Change operation reserve when the running boundary that pressure run-limiting figure limits in time, reduction as far as possible runs system and equipment unfavorable
It influences, unit is enable steadily to drop back in the range of primary Ioops temperature and pressure run-limiting figure limits to safe condition.
The embodiment of the present invention is by combining operation characteristic and run-limiting condition under one loop of nuclear power station abnormality, structure
Temperature and pressure run-limiting model under primary Ioops abnormality is built, naturally circulated condition, fault condition and accident work are drawn out
Primary Ioops temperature and pressure run-limiting figure under condition, based on primary Ioops under these run-limiting figures building failure and accident conditions
Operating status automatic tracking method can assist operator in execution accident using the latter loop state automatic tracking method of accident
The convenient operating status for intuitively monitoring primary Ioops, tracks the evolutionary process and trend of primary Ioops state during operating standard,
Suitable operation reserve is adjusted according to accident operating standard in time when operating point is located in different regions, primary Ioops state is made to begin
Eventually under monitoring, smoothly drop back to safe condition.
The serial number of the above embodiments of the invention is only for description, does not represent the advantages or disadvantages of the embodiments.
It should be understood that one loop of nuclear power station abnormality Tracking monitoring system provided by the above embodiment is realizing core
When the primary Ioops abnormality tracing and monitoring method of power station, only the example of the division of the above functional modules, actually answer
In, it can according to need and be completed by different functional modules above-mentioned function distribution, i.e., divide the internal structure of equipment
At different functional modules, to complete all or part of the functions described above.In addition, nuclear power station provided by the above embodiment
Primary Ioops abnormality Tracking monitoring system and one loop of nuclear power station abnormality tracing and monitoring embodiment of the method belong to same structure
Think, specific implementation process is detailed in embodiment of the method, and which is not described herein again.
Those of ordinary skill in the art will appreciate that realizing that all or part of the steps of above-described embodiment can pass through hardware
It completes, relevant hardware can also be instructed to complete by program, the program can store in a kind of computer-readable
In storage medium, storage medium mentioned above can be read-only memory, disk or CD etc..
The foregoing is merely presently preferred embodiments of the present invention, is not intended to limit the invention, it is all in spirit of the invention and
Within principle, any modification, equivalent replacement, improvement and so on be should all be included in the protection scope of the present invention.
Claims (10)
1. a kind of one loop of nuclear power station abnormality tracing and monitoring method, which is characterized in that the described method includes:
According to the operation characteristic and run-limiting condition under preset one loop of nuclear power station abnormality, primary Ioops exception shape is constructed
Temperature and pressure run-limiting model under state；
According to the primary Ioops main pump operating status of nuclear power station, the accident operating standard state and P signal state that are carrying out,
Select corresponding primary Ioops temperature and pressure run-limiting model, the P signal is for influencing nuclear plant safety injecting systems
Trigger condition；
The operating status of one loop of nuclear power station under abnormality is obtained, and according to temperature and pressure under the primary Ioops abnormality of selection
Power run-limiting model, adjusts the operation reserve of primary Ioops in real time, until smoothly dropping back to safe condition.
2. the method according to claim 1, wherein the abnormality includes: to lose forced circulation function
Naturally circulated condition, fault condition and accident conditions.
3. according to the method described in claim 2, it is characterized in that, when the abnormality be naturally circulated condition when, it is described
Temperature and pressure run-limiting model includes: by the saturation curve of water, primary Ioops pressure in primary Ioops under primary Ioops abnormality
Lower limit line, the high restraining line of primary Ioops pressure, primary Ioops primary side of steam generator differential pressure restraining line, primary Ioops steam generator
Secondary side differential pressure restraining line, primary Ioops temperature limiting line, primary Ioops pressurizer safety valve setting valve curve, primary Ioops Residual heat removal
Upper pressure limit restraining line, primary Ioops voltage-stablizer fluctuate after residual heat removal system connection in system access temperature limiting line, primary Ioops
The primary Ioops temperature and pressure run-limiting range that pipe thermal stress restraining line, primary Ioops minimum temperature restraining line are constituted.
4. according to the method described in claim 2, it is characterized in that, when the abnormality be fault condition when, described one time
Under the abnormality of road temperature and pressure run-limiting model include: by the saturation curve of water in primary Ioops, fault condition repair line,
The primary Ioops temperature and pressure run-limiting range that primary Ioops reduced pressure operation indication wire, primary Ioops reduced pressure operation restraining line are constituted,
The fault condition repair line includes: to forbid booster line, supercooling boundary limit value line, primary Ioops main pump restraining line.
5. according to the method described in claim 2, it is characterized in that, when the abnormality is accident conditions and the non-signal life of P
When effect, temperature and pressure run-limiting model includes: by the saturation curve of water, in primary Ioops under the primary Ioops abnormality
Restraining line, the first operation ceiling restriction line, primary Ioops Pressurizer surge line are repaired in one operation lower limit restraining line, the first accident conditions
The primary Ioops temperature and pressure run-limiting range that thermal stress restraining line is constituted；
When the abnormality is accident conditions and P signal comes into force, temperature and pressure is run under the primary Ioops abnormality
Limited model includes: by the saturation curve of water, the second operation lower limit restraining line, the second accident conditions reparation limitation in primary Ioops
The primary Ioops temperature and pressure run-limiting that line, the second operation ceiling restriction line, a back pressure force container thermal stress restraining line are constituted
Range.
6. a kind of one loop of nuclear power station abnormality Tracking monitoring system characterized by comprising
Module is constructed, for according to the operation characteristic and run-limiting condition under preset one loop of nuclear power station abnormality, structure
Build temperature and pressure run-limiting model under primary Ioops abnormality；
Selecting module, for according to the primary Ioops main pump operating status of nuclear power station, the accident operating standard state being carrying out, with
And P signal state, to select corresponding primary Ioops temperature and pressure run-limiting model, the P signal is for influencing nuclear power station
The trigger condition of safety injection system；
Processing module, for obtaining the operating status of one loop of nuclear power station under abnormality, and according to the primary Ioops of selection exception
Temperature and pressure run-limiting model under state, adjusts the operation reserve of primary Ioops in real time, until smoothly dropping back to safe shape
State.
7. system according to claim 6, which is characterized in that the abnormality includes: to lose forced circulation function
Naturally circulated condition, fault condition and accident conditions.
8. system according to claim 7, which is characterized in that described when the abnormality is naturally circulated condition
Temperature and pressure run-limiting model includes: by the saturation curve of water, primary Ioops pressure in primary Ioops under primary Ioops abnormality
Lower limit line, the high restraining line of primary Ioops pressure, primary Ioops primary side of steam generator differential pressure restraining line, primary Ioops steam generator
Secondary side differential pressure restraining line, primary Ioops temperature limiting line, primary Ioops pressurizer safety valve setting valve curve, primary Ioops Residual heat removal
Upper pressure limit restraining line, primary Ioops voltage-stablizer fluctuate after residual heat removal system connection in system access temperature limiting line, primary Ioops
The primary Ioops temperature and pressure run-limiting range that pipe thermal stress restraining line, primary Ioops minimum temperature restraining line are constituted.
9. system according to claim 7, which is characterized in that when the abnormality is fault condition, described one time
Under the abnormality of road temperature and pressure run-limiting model include: by the saturation curve of water in primary Ioops, fault condition repair line,
The primary Ioops temperature and pressure run-limiting range that primary Ioops reduced pressure operation indication wire, primary Ioops reduced pressure operation restraining line are constituted,
The fault condition repair line includes: to forbid booster line, supercooling boundary limit value line, primary Ioops main pump restraining line.
10. system according to claim 7, which is characterized in that when the abnormality is accident conditions and the non-signal life of P
When effect, temperature and pressure run-limiting model includes: by the saturation curve of water, in primary Ioops under the primary Ioops abnormality
Restraining line, the first operation ceiling restriction line, primary Ioops Pressurizer surge line are repaired in one operation lower limit restraining line, the first accident conditions
The primary Ioops temperature and pressure run-limiting range that thermal stress restraining line is constituted；
When the abnormality is accident conditions and P signal comes into force, temperature and pressure is run under the primary Ioops abnormality
Limited model includes: by the saturation curve of water, the second operation lower limit restraining line, the second accident conditions reparation limitation in primary Ioops
The primary Ioops temperature and pressure run-limiting that line, the second operation ceiling restriction line, a back pressure force container thermal stress restraining line are constituted
Range.
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110085340A (en) * | 2019-04-22 | 2019-08-02 | 中国核电工程有限公司 | A kind of nuclear power plant supports security function identification method when system is unavailable |
| CN110136852A (en) * | 2019-04-30 | 2019-08-16 | 中广核核电运营有限公司 | A kind of one loop of nuclear power station water pressure test overpressure protection system |
| CN110826217A (en) * | 2019-11-01 | 2020-02-21 | 西安交通大学 | Method for calculating safety valve threshold of reactor cold overpressure pressure stabilizer |
| CN111967711A (en) * | 2020-07-07 | 2020-11-20 | 中国核电工程有限公司 | Method for determining unfavorable working conditions in containment related to accident strategy of pressurized water reactor nuclear power plant |
| CN113628770A (en) * | 2021-08-18 | 2021-11-09 | 上海核工程研究设计院有限公司 | Real-time monitoring system for pressure and temperature limit of nuclear power plant |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102279901A (en) * | 2011-05-17 | 2011-12-14 | 湖北省电力公司电力试验研究院 | Modeling method specific to third generation pressurized water reactor nuclear power generating unit |
| CN103714870A (en) * | 2013-12-13 | 2014-04-09 | 中国核电工程有限公司 | Design method of nuclear power plant serious accident instrumentation and control system |
| CN104299659A (en) * | 2013-07-16 | 2015-01-21 | 中广核工程有限公司 | Method, device and system for monitoring running state of nuclear power plant |
| US20170269580A1 (en) * | 2014-10-22 | 2017-09-21 | Mitsubishi Electric Corporation | Remote Integrated Monitoring Operation System |
| CN108231227A (en) * | 2017-12-18 | 2018-06-29 | 广东核电合营有限公司 | A kind of monitoring method, system and the storage medium of nuclear power station operating status |
| CN108389639A (en) * | 2017-09-30 | 2018-08-10 | 深圳中广核工程设计有限公司 | Nuclear plant digital is normal and system and method are arranged in accident operating standard interface |
-
2018
- 2018-11-08 CN CN201811324095.7A patent/CN109524140B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102279901A (en) * | 2011-05-17 | 2011-12-14 | 湖北省电力公司电力试验研究院 | Modeling method specific to third generation pressurized water reactor nuclear power generating unit |
| CN104299659A (en) * | 2013-07-16 | 2015-01-21 | 中广核工程有限公司 | Method, device and system for monitoring running state of nuclear power plant |
| CN103714870A (en) * | 2013-12-13 | 2014-04-09 | 中国核电工程有限公司 | Design method of nuclear power plant serious accident instrumentation and control system |
| US20170269580A1 (en) * | 2014-10-22 | 2017-09-21 | Mitsubishi Electric Corporation | Remote Integrated Monitoring Operation System |
| CN108389639A (en) * | 2017-09-30 | 2018-08-10 | 深圳中广核工程设计有限公司 | Nuclear plant digital is normal and system and method are arranged in accident operating standard interface |
| CN108231227A (en) * | 2017-12-18 | 2018-06-29 | 广东核电合营有限公司 | A kind of monitoring method, system and the storage medium of nuclear power station operating status |
Non-Patent Citations (1)
| Title |
|---|
| H.M.HASHEMIAN: "On-line monitoring applications in nuclear power plants", 《PROGRESS IN NUCLEAR ENERGY》 * |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110085340A (en) * | 2019-04-22 | 2019-08-02 | 中国核电工程有限公司 | A kind of nuclear power plant supports security function identification method when system is unavailable |
| CN110085340B (en) * | 2019-04-22 | 2020-11-06 | 中国核电工程有限公司 | Execution method for nuclear power plant when support system is unavailable |
| CN110136852A (en) * | 2019-04-30 | 2019-08-16 | 中广核核电运营有限公司 | A kind of one loop of nuclear power station water pressure test overpressure protection system |
| CN110136852B (en) * | 2019-04-30 | 2020-08-07 | 中广核核电运营有限公司 | Nuclear power station primary loop hydrostatic test overpressure protection system |
| CN110826217A (en) * | 2019-11-01 | 2020-02-21 | 西安交通大学 | Method for calculating safety valve threshold of reactor cold overpressure pressure stabilizer |
| CN110826217B (en) * | 2019-11-01 | 2021-08-13 | 西安交通大学 | Method for calculating safety valve threshold of reactor cold overpressure pressure stabilizer |
| CN111967711A (en) * | 2020-07-07 | 2020-11-20 | 中国核电工程有限公司 | Method for determining unfavorable working conditions in containment related to accident strategy of pressurized water reactor nuclear power plant |
| CN113628770A (en) * | 2021-08-18 | 2021-11-09 | 上海核工程研究设计院有限公司 | Real-time monitoring system for pressure and temperature limit of nuclear power plant |
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