CN109147967A - A kind of boron concentration control apparatus and method for nuclear power station - Google Patents
A kind of boron concentration control apparatus and method for nuclear power station Download PDFInfo
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- CN109147967A CN109147967A CN201710452611.3A CN201710452611A CN109147967A CN 109147967 A CN109147967 A CN 109147967A CN 201710452611 A CN201710452611 A CN 201710452611A CN 109147967 A CN109147967 A CN 109147967A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/22—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of a fluid or fluent neutron-absorbing material, e.g. by adding neutron-absorbing material to the coolant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/032—Reactor-coolant flow measuring or monitoring
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
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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
- Y02E30/30—Nuclear fission reactors
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Abstract
A kind of boron concentration control apparatus and method for nuclear power station, the device include valve regulated module (3), valve (4) and boron flow monitor (5).Coolant boron flow value in one loop of nuclear power station is monitored according to boron flow monitor, is injected into borated coolant in primary Ioops from boron tank by valve regulated module control valve aperture, to realize the control to coolant boron concentration in one loop of nuclear power station.The problem of which solves nuclear power station unit station primary Ioops when the end of term in longevity carrying out changing water, and self-sustained oscillation adjusting occurs in valve, and reactor-loop is caused to be subcooled and overheat.It can solve same problem existing for other nuclear power station same type units.The present invention improves nuclear-power reactor safety and stability, has major contribution to nuclear plant safety stable operation.
Description
Technical field
The present invention relates to nuclear power station production system thermal technics fields, and in particular to a kind of boron for nuclear power station is dense
Spend control device and method.
Background technique
Power plant using nuclear energy production electric energy is known as nuclear power plant.PWR nuclear power plant is mainly by pressurized water reactor, reactor
Coolant system (abbreviation primary Ioops), steam and power conversion system (abbreviation secondary circuit), circulation, generator and transmission & distribution
Electric system and its auxiliary system composition.Primary Ioops and nuclear island auxiliary system, engineered safeguards features and workshop are usually known as nuclear island.
Secondary circuit and its auxiliary system and workshop are similar to conventional thermal power plant system and equipment, referred to as conventional island.The other parts of power plant,
It is referred to as auxiliary facility.
Reactor core because fuel fission generates huge thermal energy, by the water that main pump is pumped into reactor core be heated to form 327 degree,
The high-temperature high pressure water of 155 atmospheric pressure, high-temperature high pressure water flow through the heat transfer U-tube in steam generator, by tube wall by thermal energy
It passes to the secondary circuit cooling water outside U-tube, discharges to send reactor core back to by main pump again after heat and reheat and enter back into steam generation
Device, water constantly recycle in closed circuit in this way.
In order to guarantee the safe operation of reactor and reactor coolant loop, nuclear power plant is also provided with engineered safeguards features
With a series of auxiliary systems.Primary Ioops auxiliary system is mainly used to guarantee the normal operation of reactor and primary Ioops system.Press water
Heap nuclear power plant primary Ioops auxiliary system presses its function division, the system and waste treatment system of guaranteed normal operation, and part is
System while the support system as engineered safeguard system.Engineered safeguards features provide necessary answer for some great accidents
Anxious cooling provision, and prevent the diffusion of radioactive substance.
Boron is a kind of neutron absorber, and the nuclear fission of pressurised water reactor can also be by adjusting in primary Ioops in coolant
Boron concentration controls.When reactor start-up and after reach set power, critical state can be maintained, to ensure its stable fortune
Make.When needing emergency shut-down, the mechanical power supply of control rod driving need only be cut off, control rod will due to force of gravity quickly under
Pendant stops nuclear fission to reactor core immediately.
Certain nuclear power unit in the end of term in longevity because the boron concentration in primary Ioops is lower, when unit in the end of term in longevity because elemental lithium content is super
When needing to carry out changing water to primary Ioops after mark, it may appear that actual boron flow and boron flow setting value into primary Ioops exist partially
Difference, once deviation it is larger will the nuclear reactor reactivity to one loop of nuclear power station have an impact.Primary Ioops it is actual
Boron flow, which is greater than boron flow setting value, will lead to that primary Ioops are colder, and the actual boron flow of primary Ioops is less than the meeting of boron flow setting value
Lead to primary Ioops partial heat, the result of most serious would be possible to the movement for leading to primary Ioops temperature control rod.
There is also same problems for current nuclear power station same type units, when boron actual flow is far smaller than boron flow given value
The reactivity of primary Ioops reactor core overheats, and nuclear reactor shutdown is also resulted in when serious.
Summary of the invention
The application provides a kind of boron concentration control apparatus and method for nuclear power station, for accurately controlling to adjust nuclear power station
The concentration of coolant boron in primary Ioops, and solve nuclear power station unit station and entering the end of term in longevity, what vibrating occurred in valve automatic adjustment asks
Topic improves the running safety and stability of nuclear power station.
According to a first aspect of the present application, this application provides a kind of boron concentration control apparatus for nuclear power station, including
Boron flow monitor, valve and valve regulated module；
The boron flow monitor is for being arranged in primary Ioops, for monitoring the boron stream of coolant in the primary Ioops
Amount；
The valve is used for the access being arranged between boron tank output channel and primary Ioops coolant inlet, the valve
The aperture of door is adjustable, by adjusting the injection flow of the coolant in the controllable injection primary Ioops of aperture；
The boron flow that the valve regulated module is used to monitor the boron flow monitor gives with boron flow
Value is compared, and the aperture of the valve is controlled according to comparison result, the aperture minimum value of the valve is 0%, the valve
Maximum value be 100%.
Further, the boron flow given value be in primary Ioops the product of boron actual concentrations and a coefficient divided by the boron tank
The obtained quotient of difference of the boron concentration of middle coolant and the boron actual concentrations, wherein the boron actual concentrations are described in injection
The boron concentration in the primary Ioops in boron tank before coolant.
In one embodiment, the valve regulated module exports DC current signal according to the comparison result, by straight
Current signal is flowed to control the valve opening.
According to a second aspect of the present application, the application also provides a kind of method that the boron concentration for nuclear power station controls, packet
It includes:
Measure the boron flow of coolant in primary Ioops；
The boron flow in the coolant monitored according to the boron flow monitor is compared with boron flow given value
As a result, carrying out control valve aperture；
Valve is opened according to the valve opening, to control the injection flow for the coolant being injected into the primary Ioops.
The device and method of the boron concentration control of the coolant of one loop of nuclear power station provided by the present application, due to according to one time
The comparison result of coolant boron flow and boron flow given value in road sets valve opening, and then controls and be injected into primary Ioops
The injection flow of middle coolant, to realize that the boron concentration to coolant in primary Ioops controls.
Detailed description of the invention
Fig. 1 is a kind of structural schematic diagram of boron concentration control apparatus for nuclear power station provided in an embodiment of the present invention；
Fig. 2 is a kind of flow chart of the boron concentration control method for nuclear power station provided in an embodiment of the present invention；
Fig. 3 is the partial circuit connection figure of another embodiment Nuclear Power Station reactor REA system of the present invention；
Fig. 4 is the valve regulated effect operation curve figure of another embodiment Nuclear Power Station reactor REA system of the present invention；
Fig. 5 is the valve regulated effect operation curve figure of another embodiment Nuclear Power Station reactor REA system of the present invention；
Fig. 6 is the valve regulated effect operation curve figure of another embodiment Nuclear Power Station reactor REA system of the present invention；
Fig. 7 is the valve regulated effect operation curve figure of another embodiment Nuclear Power Station reactor REA system of the present invention；
Fig. 8 is the valve regulated effect operation curve figure of another embodiment Nuclear Power Station reactor REA system of the present invention.
Specific embodiment
In order to make the objectives, technical solutions, and advantages of the present invention clearer, with reference to the accompanying drawings and embodiments, right
The present invention is further elaborated.It should be appreciated that the specific embodiments described herein are merely illustrative of the present invention, and
It is not used in the restriction present invention.
As shown in Figure 1, a kind of structural schematic diagram of the boron concentration control apparatus for nuclear power station in the present invention.One kind is used for
The boron concentration control apparatus of nuclear power station includes: boron flow monitor 2, valve regulated module 3 and valve 4.
Primary Ioops 1 are that nuclear reactor is generated huge heat for recycling in closed circuit by coolant
The system that can be passed；Boron tank 5 is for storing the coolant 6 containing boron；Boron flow monitor 2 is cold in primary Ioops for monitoring
But the boron flow of agent；The boron in the coolant in primary Ioops that valve regulated module 3 is used to be monitored according to boron flow monitor 2
The comparison result of flow and boron flow given value comes the aperture and aperture range of control valve 4；Valve 4 in boron tank 5 for will contain
There is the coolant 6 of boron to be injected into primary Ioops 1, wherein be injected into the injection flow of the coolant 6 in primary Ioops 1 containing boron by
4 aperture of valve determines.
The aperture of valve 4 is adjustable, by adjusting the injection flow of the coolant in the controllable injection primary Ioops of aperture, works as valve
When door aperture is 0%, the injection flow for being injected into the coolant 6 in primary Ioops 1 containing boron is 0 l/h, when valve opening is
When 100%, the injection flow for being injected into the coolant 6 in primary Ioops 1 containing boron is 15 ls/h.Specifically, according to boron flow
The percentage number that the value and boron flow given value for the boron flow that monitor 2 monitors ask quotient to obtain, 3 output phase of valve regulated module
The DC current signal control valve 4 answered opens corresponding aperture.For example, the value of the boron flow monitored is 0 l/h, i.e.,
The percentage number that the value and boron flow given value for the boron flow that boron flow monitor 2 monitors ask quotient to obtain is 0%, valve regulated
Module 3 exports the smallest 4 aperture of DC current signal control valve and fully opens for 100%.When boron flow monitor 2 monitors
The value of boron flow be boron flow given value, i.e., the value of boron flow that boron flow monitor 2 monitors is asked with boron flow given value
The percentage number that quotient obtains is 100%, and it is 0% that valve regulated module 3, which exports maximum 4 aperture of DC current signal control valve,
It completely closes.
In the present embodiment, the aperture minimum value of 3 control valve 4 of valve regulated module is 5.9%, and aperture maximum value is
100%, and then the injection flow minimum of coolant controlled in injection primary Ioops is 0.1 l/h, maximum value is 15 liters/
Hour.
In addition, the coolant boron concentration in boron tank can be 7000 micro- gram grams.Coolant can be boron and water in primary Ioops
Mixed liquor, can also be other liquid such as heavy water.
The device that a kind of boron concentration for nuclear power station provided by the present application controls, due in the coolant according to primary Ioops
The comparison result of boron flow and boron flow given value sets valve opening, and then controls to be injected into primary Ioops and contain boron
Primary Ioops coolant injection flow, with realize in primary Ioops coolant boron concentration control.
As shown in figure 3, the present embodiment is nuclear reactor REA (Reator Boron and Water Makeup) reactor
The partial circuit connection figure of the make-up system of boron and water, including:
Valve regulated module 1, given value input unit 2, valve 3 and boron flow monitor 4.Wherein, valve regulated module 1
It can be adjustment module PID (Proport ion Integrat ion Differentiat ion), given value input unit 2
It can be REA401KU, valve 3 can be REA065VB, and boron flow monitor 4 can be REA059MD.
REA system is in stoppage in transit state when nuclear power station unit station operates normally.
REA system operation mode has automatic supply, manual supply, primary Ioops to change water, independent boronation and individually dilute several
The method of operation.Supply is that operator is fed manually according to conditions of demand of the one loop of nuclear power station to coolant manually.One time
Lu Huanshui is to be carried out changing water according to elemental lithium situation in the coolant in primary Ioops, eliminates elemental lithium to reactor core reaction
Influence.Independent boronation is to carry out boronation operation after power drops in nuclear power station unit station to eliminate xenon poison in the coolant in primary Ioops.
Individually dilution is diluted to the coolant in primary Ioops, to reduce the boron concentration of coolant in primary Ioops, to promote nuclear power
The power for core of standing solves the problems, such as the too low supercooling of coolant temperature in primary Ioops.Automatic supply is since nuclear power station one returns
The automatic running supply of the very few triggering REA system of road coolant, it is automatic after meeting the requirements to stop transport.
When REA system is not run, valve 3 is in full off state.The safe condition of valve 3 is standard-sized sheet, refers to that power loss loses gas
Valve 3 is in automatic full-gear when state, and case of emergency occur can be cold by the boracic for weakening nuclear reactor core reaction
But agent is injected into primary Ioops, guarantees nuclear plant safety.
There are two types of control modes for valve 3, and one is guarantee that gas source is entered valve cylinder for valve by valve by solenoid valve
Door is closed.Another kind is that valve regulated module 1 automatically adjusts to the aperture of valve 3 by the direct current signal of 4-20mA, valve
The aperture maximum value of door 3 is 100%, and minimum value is 0%.When the aperture of valve 3 is 100%, expression valve is fully opened, and works as valve
The aperture of door 3 is 0%, indicates that valve completely closes.
When REA system not running, operator needs to go out boron flow according to the boron concentration conversion of coolant in primary Ioops given
Value, conversion method be coolant in primary Ioops boron concentration value and coefficient product divided by coolant in boron tank boron concentration value with
The obtained quotient of difference of the boron concentration value of coolant, the coefficient can be 10 in primary Ioops.Such as following formula:
Boron flow given value is input in valve regulated module 1 by given value input unit 2, if boron flow monitoring
The monitoring flow of device 4 is zero, then boron flow given value is greater than boron flow value (the subsequent title monitoring of the monitoring of boron flow monitor 4
Value), leading to the aperture of 1 control valve 3 of valve regulated module is maximum value 100%.
When REA system runs any mode, such as supply manually, water etc. is changed all the way, since valve 3 is to beat completely
It opens, monitor value is leapt high in the moment that REA system has just brought into operation more than boron flow given value, then in valve regulated module 1
Aperture is gradually reduced in control lower valve 3, so that monitor value gives gradually close to boron flow given value when monitor value reaches boron flow
When value, closes system and complete self-regulating process.
If after REA system end of run, when the actual boron flow of primary Ioops is greater than boron flow setting value, core can be made anti-
Heap reactor core reactivity is answered to die down, it is colder so as to cause one loop of nuclear power station.The boron flow entered in primary Ioops in order to prevent is greater than
Boron flow given value, in REA system operation, when the coolant injection flow value being injected into primary Ioops is greater than boron flow
When given value and 0.3 l/h of sum continue 30 seconds, deviation alarm will be triggered, 1 control valve 3 of valve regulated module is closed.
If after REA system end of run, when the actual boron flow of primary Ioops is less than boron flow setting value, core can be made anti-
Heap reactor core reactivity is answered to become strong, so as to cause one loop of nuclear power station partial heat.The boron flow entered in primary Ioops in order to prevent is less than
Boron flow given value, in REA system operation, when the coolant injection flow value being injected into primary Ioops is less than boron flow
When given value and 0.3 l/h of difference continue 30 seconds, deviation alarm will be triggered, 1 control valve 3 of valve regulated module is closed.
Nuclear power station unit station enters the end of term in longevity, and the boron concentration of coolant can continue to decline in primary Ioops.When REA system carries out one
When water running is changed in circuit, according to boron flow given value conversion method, the boron flow given value conversed is lower (to be reached when minimum
0.2 l/h).Under normal conditions, when boron flow given value is less than 0.8 l/h, when REA system brings into operation, valve tune
The aperture for saving 1 control valve 3 of module is maximum value 100%, and then controls the injection flow 15 of the coolant in injection primary Ioops
L/h, the monitor value moment of boron flow monitor 4 leaps high, and is far longer than boron flow given value, controls valve regulated module 1
3 rapid drop aperture of valve processed to minimum value 0%, at this time the monitor value of boron flow monitor 4 be far smaller than again boron flow to
Definite value, and 1 control valve 3 of valve regulated module is made quickly to increase aperture, at this moment the monitor value of boron flow monitor 4 is again much big
In boron flow given value, valve regulated module 1 and 3 rapid drop aperture of control valve.Thus it recycles, valve 3 is caused to will appear
Sustained oscillation is adjusted, i.e., being far longer than boron flow given value into primary Ioops boron actual flow primary Ioops reactivity occurred
It is cold, or being far smaller than boron flow given value into primary Ioops boron actual flow overheats primary Ioops reactivity.Therefore valve 3 is adjusted
Effect is poor directly affects the reactive stability of primary Ioops for section.
As shown in figure 4, Fig. 4 shows the aperture minimum value of 1 control valve 3 of valve regulated module when being 0%, the tune of valve
Effect operation curve figure is saved, line 1 is 3 opening curve of valve, and line 2 is the monitor value curve of boron flow monitor 4.When boron flow is fixed
Value all such sustained oscillation operation curves at 0.8 l/h or less.When the end of term in unit longevity, primary Ioops change water according to boron
The boron flow given value that flow given value conversion method obtains all will be less than 0.8 l/h.
To solve the above-mentioned problems, the embodiment of the present invention provides another embodiment, when boron flow given value is not more than
0.8 l/h, 1 control valve of valve regulated module, 3 aperture minimum value is set as 5.9% by original 0%, and then controls note
The injection range of flow for entering the coolant in the primary Ioops becomes 0.1-15 ls/h from 0-15 ls/h.Even if practical boron
Flow drops to 0.1 l/h of minimum value, and (the practical boron flow that test data show that boron flow monitor 4 monitors can be stablized
Just no longer decline at 0.1 l/h of minimum value, if valve continues to close, at this moment 0) boron actual flow can drop to, valve regulated
The opening degree instruction that module 1 passes through DC signal output to valve 3 is 5.9%, and 1 bottoming of valve regulated module is instructed by original
0% come is adjusted to 5.9%, so that 3 aperture of valve is no longer reduced when being reduced to 5.9%, to no longer make under boron actual flow
0 l/h is dropped to, the regulating time of 1 control valve of valve regulated module, 3 aperture from 5.9% to 0%, and then valve have been saved
It does not turn off to complete and closes, it is lower (less than 0.8m3/ in boron flow rate set value fundamentally to solve REA system boron flow control valve yet
The problem of sustained oscillation when h).
When REA system brings into operation, the aperture of 1 control valve 3 of valve regulated module is 15 ls/h of maximum value, boron stream
The monitor value moment of amount monitor 4 leaps high, and is far longer than boron flow given value, so that valve regulated module 1 is controlled boron flow and adjusts
3 rapid drop aperture of valve is no longer 0% PID output order before modification, boron actual flow to 5.9% PID output order
Minimum drops to 0.1 l/h, rather than 0 l/h before modifying, the monitor value of boron flow monitor 4 will not be much at this time
Boron flow given value has been less than it, therefore 1 control valve 3 of valve regulated module slowly increases aperture to boron flow given value, completes
Self-regulating process meets the REA system service requirement interim in the unit entire longevity.
It wherein, is output 3 aperture of direct current signal control valve of PID regulator by original 0% by valve control module 1
It is set as 5.9%, is verified by a large number of experiments, which is to establish the critical value of practical boron flow, is needed according to every unit
The different discharge characteristic of boron flow control valve is obtained by test.
As shown in figure 5, Fig. 5 shows the aperture minimum value of 1 control valve 3 of valve regulated module when being 5.9%, valve
Regulating effect operation curve figure, line 1 are 3 opening curves of valve, and line 2 is the monitor value curve of boron flow monitor 4.When boron flow
Definite value is at 0.8 l/h or less, sustained oscillation operation curve not similar to Figure 4.
As shown in fig. 6, being the regulating effect operation curve figure that late gate is implemented in the invention, line 1 is 3 opening curve of valve,
Line 2 is the monitor value curve of boron flow monitor 4.When boron flow given value is at 0.8 l/h or less, all such fortune
Row curve.Boron flow rate set value entirely reaches such regulating effect at 0.2 l/h or more, fully meets the unit entire phase in longevity
The requirement of last REA system operation.
As shown in fig. 7, being to carry out changing water operation before the invention is implemented, the regulating effect operation curve figure of valve, line 1 is valve
3 opening curves of door, line 2 is the monitor value curve of boron flow monitor 4.Boron flow rate set value is 0.23 l/h, due to boron flow
Definite value is close to minimum, so valve 3 occurs irregularly shaking adjustment.
As shown in figure 8, being to carry out changing water operation after the invention is implemented, the regulating effect operation curve figure of valve, line 1 is valve
3 opening curves of door, line 2 is the monitor value curve of boron flow monitor 4.Boron flow rate set value is 0.23 l/h, is adjusted well,
Solve the problem of lower lower concussion of signals is adjusted.
The embodiment of the present invention solves nuclear power station unit station primary Ioops when the end of term in longevity carrying out changing water, and self-sustained oscillation occurs in valve
The problem of adjusting, reactor-loop caused to be subcooled and overheat.It can solve identical existing for other nuclear power station same type units ask
Topic.The present invention improves nuclear-power reactor safety and stability, has major contribution to nuclear plant safety stable operation.
The embodiment of the present invention a kind of boron concentration control method for nuclear power station is provided as shown in Fig. 2, this method include with
Lower step:
S201: the boron concentration of coolant in measurement primary Ioops.
S202: according to the concentration calculation boron concentration given value of measurement.
Boron flow given value is that boron actual concentrations and the product of a coefficient are dense divided by the boron of coolant in boron tank in primary Ioops
The obtained quotient of difference of degree and boron actual concentrations, wherein boron actual concentrations are that the boron in the primary Ioops before injecting coolant is dense
Degree.
S203: setting valve opening minimum value is 5.9%.
S204 opens valve, and the boron flow in the coolant monitored according to boron flow monitor gives with boron flow
The comparison result of value carrys out control valve aperture, and then controls the injection flow for the coolant being injected into the primary Ioops.
S205: the boron flow that boron flow monitor continues to measure in primary Ioops measures monitor value, and monitor value is given with boron flow
Definite value is identical.
S206: valve is closed.
Above-mentioned operation method so that the aperture of valve is controlled, and then controls and is injected into coolant in primary Ioops
Flow is injected, to realize that the boron concentration to coolant in primary Ioops controls.
Use above specific case is illustrated the present invention, is merely used to help understand the present invention, not to limit
The system present invention.For those skilled in the art, according to the thought of the present invention, can also make several simple
It deduces, deform or replaces.
Claims (12)
1. a kind of boron concentration control apparatus for nuclear power station, the boron concentration control apparatus is for controlling coolant in primary Ioops
In boron concentration, it is characterised in that: including boron flow monitor, valve and valve regulated module；
The boron flow monitor is for being arranged in primary Ioops, for monitoring the boron flow of coolant in the primary Ioops；
The valve is used for the access being arranged between boron tank output channel and primary Ioops coolant inlet, the valve
Aperture is adjustable, by adjusting the injection flow of the coolant in the controllable injection primary Ioops of aperture；
The valve regulated module be used for the boron flow that monitors the boron flow monitor and boron flow given value into
Row compares, and the aperture of the valve is controlled according to comparison result, the aperture minimum value of the valve is 0%, and the valve is most
Big value is 100%.
2. a kind of boron concentration control apparatus for nuclear power station as described in claim 1, which is characterized in that the boron flow is given
Value is that the product of boron actual concentrations and a coefficient is practical divided by the boron concentration of coolant in the boron tank and the boron in primary Ioops
The obtained quotient of the difference of concentration, wherein the boron actual concentrations are the primary Ioops in the injection boron tank before coolant
In boron concentration.
3. a kind of boron concentration control apparatus for nuclear power station as described in claim 1, which is characterized in that the valve regulated mould
Root tuber exports DC current signal according to the comparison result, and the valve opening is controlled by DC current signal.
4. a kind of boron concentration control apparatus for nuclear power station as claimed in claim 3, which is characterized in that according to the boron flow
The percentage number that the value for the boron flow that monitor monitors and the boron flow given value ask quotient to obtain, the valve regulated
Module exports corresponding DC current signal and controls the corresponding aperture of the valve opening.
5. a kind of boron concentration control apparatus for nuclear power station as described in any one of claims 1 to 4, which is characterized in that institute
Stating valve regulated module and controlling the aperture minimum value of the valve is 5.9%.
6. a kind of boron concentration control apparatus for nuclear power station as described in any one of claims 1 to 4, which is characterized in that institute
It states in boron concentration control apparatus operational process, is held when the injection flow for the coolant being injected into the primary Ioops is greater than the first value
When continuous first predetermined amount of time, it is 0% that the valve regulated module, which exports the DC current signal to carry out the aperture of control valve,
Wherein, first value is the particular value greater than the boron flow given value.
7. a kind of boron concentration control apparatus for nuclear power station as described in any one of claims 1 to 4, which is characterized in that institute
It states in boron concentration control apparatus operational process, when the injection flow for the coolant being injected into the primary Ioops is held less than second value
When continuous second predetermined amount of time, it is 0% that the valve regulated module, which exports the DC current signal to carry out the aperture of control valve,
Wherein, the second value is the particular value less than the boron flow given value.
8. a kind of boron concentration control apparatus for nuclear power station as described in claim 1, which is characterized in that the coolant is boron
With the mixed liquor of water.
9. a kind of boron concentration control apparatus for nuclear power station as described in claim 1, which is characterized in that contain in the boron tank
Boron concentration is 7000 micro- gram grams in the coolant of boron.
10. a kind of boron concentration control method for nuclear power station, which comprises the following steps:
Measure the boron flow of coolant in primary Ioops；
The comparison result of the boron flow and boron flow given value in the coolant monitored according to the boron flow monitor,
Carry out control valve aperture；
Valve is opened according to the valve opening, to control the injection flow for the coolant being injected into the primary Ioops.
11. a kind of boron concentration control method for nuclear power station as claimed in claim 10, which is characterized in that the method is also wrapped
It includes:
The boron flow given value be coolant in primary Ioops boron actual concentrations and a coefficient product divided by the boron tank
The obtained quotient of difference of the boron concentration of coolant containing boron and the boron actual concentrations, wherein the boron actual concentrations are notes
Enter the boron concentration in the primary Ioops in the boron tank before coolant.
12. a kind of boron concentration control method for nuclear power station as claimed in claim 10, which is characterized in that the method is also wrapped
It includes:
The aperture minimum value for setting the valve is 5.9%.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710452611.3A CN109147967B (en) | 2017-06-15 | 2017-06-15 | Boron concentration control device and method for nuclear power station |
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| CN109887554A (en) * | 2019-03-13 | 2019-06-14 | 广西防城港核电有限公司 | The calculation method of nuclear reactor primary Ioops coolant Critical Solution boron content |
| CN110096076A (en) * | 2019-04-25 | 2019-08-06 | 岭东核电有限公司 | Million kilowatt nuclear power station boron feeds control circuit, device and method |
| CN112858376A (en) * | 2021-01-04 | 2021-05-28 | 广西防城港核电有限公司 | Method for measuring content of dissolved hydrogen in reactor primary loop |
| WO2022105356A1 (en) * | 2020-11-20 | 2022-05-27 | 西安热工研究院有限公司 | Method and system, having incremental adjustment function, for adjusting control rod of nuclear power unit |
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