CN109147967B - Boron concentration control device and method for nuclear power station - Google Patents

Boron concentration control device and method for nuclear power station Download PDF

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Publication number
CN109147967B
CN109147967B CN201710452611.3A CN201710452611A CN109147967B CN 109147967 B CN109147967 B CN 109147967B CN 201710452611 A CN201710452611 A CN 201710452611A CN 109147967 B CN109147967 B CN 109147967B
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boron
valve
coolant
flow
value
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CN109147967A (en
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刘明臣
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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China General Nuclear Power Corp
CGN Power Co Ltd
Daya Bay Nuclear Power Operations and Management Co Ltd
Guangdong Nuclear Power Joint Venture Co Ltd
Lingao Nuclear Power Co Ltd
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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
    • 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
    • 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
    • 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
    • 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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  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
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Abstract

A boron concentration control apparatus and method for a nuclear power plant includes a valve adjustment module (3), a valve (4), and a boron flow monitor (5). And monitoring the boron flow value of the coolant in the nuclear power station primary loop according to the boron flow monitor, and controlling the opening of a valve by a valve adjusting module to inject the boron-containing coolant into the primary loop from the boron tank so as to realize the control of the boron concentration of the coolant in the nuclear power station primary loop. The device solves the problems that when a loop of the nuclear power station unit is changed with water at the end of the service life, the valve is adjusted by constant amplitude oscillation, so that the loop of the reactor is too cold and too hot. The same problems of the same type of units of other nuclear power stations can be solved. The invention improves the safety and stability of the nuclear power reactor and makes great contribution to the safe and stable operation of the nuclear power station.

Description

Boron concentration control device and method for nuclear power station
Technical Field
The invention relates to the field of automatic control of thermal engineering of a nuclear power station production system, in particular to a boron concentration control device and method for a nuclear power station.
Background
Plants that produce electrical energy from nuclear energy are referred to as nuclear power plants. The pressurized water reactor nuclear power plant mainly comprises a pressurized water reactor, a reactor coolant system (a primary loop for short), a steam and power conversion system (a secondary loop for short), a circulating water system, a generator, a power transmission and distribution system and auxiliary systems thereof. A loop and nuclear island auxiliary system, dedicated security facilities and plant are often referred to as a nuclear island. The secondary loop and its ancillary systems and plants are similar to conventional thermal power plant systems and equipment and are referred to as conventional islands. Other parts of the power plant are collectively called supporting facilities.
The reactor core generates huge heat energy due to fission of nuclear fuel, water pumped into the reactor core by a main pump is heated into high-temperature high-pressure water with 327 ℃ and 155 atmospheric pressures, the high-temperature high-pressure water flows through a heat transfer U-shaped pipe in a steam generator, the heat energy is transferred to two-loop cooling water outside the U-shaped pipe through a pipe wall, the high-temperature high-pressure water is returned to the reactor core by the main pump after releasing the heat energy and is reheated and then enters the steam generator, and the water continuously circulates in a closed loop.
In order to ensure the safe operation of the reactor and the reactor coolant system, the nuclear power plant is also provided with a special safety facility and a series of auxiliary systems. The primary loop auxiliary system is mainly used for ensuring the normal operation of the reactor and the primary loop system. The primary circuit auxiliary system of the pressurized water reactor nuclear power plant is divided according to the functions thereof, and is provided with a system for ensuring normal operation and a waste treatment system, and part of the systems are simultaneously used as support systems of a special safety facility system. The dedicated safety facilities provide necessary emergency cooling measures for some major accidents and prevent the diffusion of radioactive substances.
Boron is a neutron absorber and the nuclear fission of a pressurized water reactor can also be controlled by adjusting the boron concentration in the coolant in the primary circuit. When the reactor is started and reaches a predetermined power, it is maintained at a critical state to ensure stable operation. When emergency shutdown is needed, the control rod can quickly drop to the reactor core due to the ground core suction force by only cutting off the power supply of the control rod driving mechanism, and the nuclear fission is immediately stopped.
The boron concentration in a loop of a certain nuclear power unit is low at the end of the service life, when the water needs to be changed for the loop after the content of lithium element exceeds the standard at the end of the service life, the deviation between the actual boron flow entering the loop and the boron flow set value can occur, and once the deviation is large, the nuclear reactor core reactivity of the loop of the nuclear power station can be influenced. The actual boron flow of the loop being greater than the boron flow set point may result in a loop that is colder than the boron flow set point, and the actual boron flow of the loop being less than the boron flow set point may result in a loop that is hotter than the boron flow set point, with the worst result likely resulting in the actuation of the loop temperature control rods.
The same problem also exists in the current same type unit of nuclear power station, and the reactivity of a loop reactor core appears overheated when the actual flow of boron is far less than the boron flow given value, still can lead to the nuclear reactor to shut down when serious.
Disclosure of Invention
The application provides a boron concentration control device and method for a nuclear power station, which are used for accurately controlling and adjusting the concentration of coolant boron in a primary circuit of the nuclear power station, solving the problem that a valve automatically adjusts and oscillates when a nuclear power station unit enters the end of the service life, and improving the safety and stability of the nuclear power station in operation.
According to a first aspect of the present application, there is provided a boron concentration control apparatus for a nuclear power plant, comprising a boron flow monitor, a valve, and a valve adjustment module;
the boron flow monitor is arranged in a loop and used for monitoring the boron flow of coolant in the loop;
the valve is arranged on a passage between the boron tank output pipeline and a primary circuit coolant injection port, the opening degree of the valve is adjustable, and the injection flow of the coolant injected into the primary circuit can be controlled by adjusting the opening degree;
the valve adjusting module is used for comparing the boron flow monitored by the boron flow monitor with a given boron flow value and controlling the opening of the valve according to a comparison result, wherein the minimum value of the opening of the valve is 0% and the maximum value of the valve is 100%.
Further, the given boron flow value is a quotient obtained by dividing a product of an actual boron concentration in a circuit, which is the boron concentration in the circuit prior to injection of coolant into the boron tank, by a coefficient, and a difference between the boron concentration of coolant in the boron tank and the actual boron concentration.
In an embodiment, the valve adjusting module outputs a dc current signal according to the comparison result, and controls the valve opening degree through the dc current signal.
According to a second aspect of the present application, there is also provided a method of boron concentration control for a nuclear power plant, comprising:
measuring the boron flow of the coolant in the loop;
controlling the opening of a valve according to the comparison result of the boron flow in the coolant monitored by the boron flow monitor and a given boron flow value;
opening a valve in accordance with the valve opening to control an injection flow rate of the coolant injected into the circuit.
The application provides a device and method of boron concentration control of coolant of nuclear power station return circuit, owing to coolant boron flow and boron flow given value's comparison result in according to the return circuit sets for the valve opening, and then has controlled the injection flow who pours into the coolant into the return circuit to the realization is to the boron concentration control of coolant in the return circuit.
Drawings
Fig. 1 is a schematic structural diagram of a boron concentration control apparatus for a nuclear power plant according to an embodiment of the present invention;
fig. 2 is a flowchart of a boron concentration control method for a nuclear power plant according to an embodiment of the present invention;
FIG. 3 is a partial electrical circuit connection diagram of a REA system for a nuclear reactor in a nuclear power plant in accordance with another embodiment of the present invention;
FIG. 4 is a graphical illustration of a valve-throttling effect operational curve of a REA system for a nuclear reactor of a nuclear power plant in accordance with another embodiment of the present invention;
FIG. 5 is a graphical illustration of a valve-trim effect operational curve of a REA system for a nuclear reactor in a nuclear power plant in accordance with another embodiment of the present invention;
FIG. 6 is a graphical illustration of a valve-throttling effect operational curve of a REA system for a nuclear reactor of a nuclear power plant in accordance with another embodiment of the present invention;
FIG. 7 is a graphical illustration of a valve-trim effect operational curve of a REA system for a nuclear reactor in a nuclear power plant in accordance with another embodiment of the present invention;
FIG. 8 is a graphical illustration of the valve-trim effect operation of a REA system for a nuclear reactor in a nuclear power plant in accordance with another embodiment of the present invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is described in further detail below with reference to the accompanying drawings and embodiments. It should be understood that the specific embodiments described herein are merely illustrative of the invention and are not intended to limit the invention.
As shown in fig. 1, a schematic configuration diagram of a boron concentration control apparatus for a nuclear power plant according to the present invention. A boron concentration control apparatus for a nuclear power plant includes: a boron flow monitor 2, a valve regulating module 3 and a valve 4.
The primary loop 1 is a system for transferring the huge heat energy generated by the nuclear reactor core out through the circulation of a coolant in the closed loop; the boron tank 5 is used for storing coolant 6 containing boron; the boron flow monitor 2 is used for monitoring the boron flow of the coolant in the loop; the valve adjusting module 3 is used for controlling the opening and the opening range of the valve 4 according to the comparison result of the boron flow in the coolant in the loop monitored by the boron flow monitor 2 and the given boron flow value; the valve 4 is used to inject the coolant 6 containing boron in the boron tank 5 into the primary circuit 1, wherein the injection flow rate of the coolant 6 containing boron into the primary circuit 1 is determined by the degree of opening of the valve 4.
The opening degree of the valve 4 is adjustable, and the injection flow rate of the coolant into the primary circuit is controlled by adjusting the opening degree, and when the opening degree of the valve is 0%, the injection flow rate of the coolant 6 containing boron into the primary circuit 1 is 0 liter/hour, and when the opening degree of the valve is 100%, the injection flow rate of the coolant 6 containing boron into the primary circuit 1 is 15 liters/hour. Specifically, according to the percentage obtained by quotient calculation of the boron flow value monitored by the boron flow monitor 2 and the boron flow set value, the valve adjusting module 3 outputs a corresponding direct current signal to control the valve 4 to open a corresponding opening. For example, the monitored boron flow is 0 liter/hour, that is, the percentage obtained by quotient of the boron flow monitored by the boron flow monitor 2 and the boron flow set value is 0%, and the valve adjusting module 3 outputs the minimum direct current signal to control the opening of the valve 4 to be 100% and be completely opened. When the boron flow value monitored by the boron flow monitor 2 is the given boron flow value, that is, the percentage obtained by quotient of the boron flow value monitored by the boron flow monitor 2 and the given boron flow value is 100%, the valve adjusting module 3 outputs the largest direct current signal to control the opening of the valve 4 to be 0% and completely closed.
In this embodiment, the valve adjusting module 3 controls the minimum opening value of the valve 4 to be 5.9% and the maximum opening value to be 100%, and further controls the minimum injection flow rate of the coolant injected into the loop to be 0.1 l/h and the maximum injection flow rate to be 15 l/h.
Additionally, the coolant boron concentration in the boron tank may be 7000 micrograms/gram. The coolant in the primary circuit may be a mixture of boron and water, or may be other liquid such as heavy water.
The application provides a device for boron concentration control of nuclear power station, owing to in the coolant according to a return circuit boron flow and boron flow given value's comparative result, set for the valve opening, and then controlled the injection flow who pours into the return circuit coolant that contains boron in the return circuit to the realization is to the boron concentration control of coolant in the return circuit.
Referring to fig. 3, this embodiment is a circuit diagram of a part of a system for supplying Boron and Water to a reactor of a nuclear reactor rea (reactor bolt and Water makeup), including:
the device comprises a valve adjusting module 1, a set value input device 2, a valve 3 and a boron flow monitor 4. The valve regulation module 1 may be a regulation module pid (process integration differentiation), the set-point input device 2 may be REA401KU, the valve 3 may be REA065VB, and the boron flow monitor 4 may be REA059 MD.
And the REA system is in a shutdown state when the nuclear power station unit normally operates.
The REA system has several operation modes of automatic supply, manual supply, primary loop water change, independent boronization and independent dilution. The manual supply is carried out by an operator according to the demand condition of the primary loop of the nuclear power plant for the coolant. The water change of the primary loop is carried out according to the condition of lithium element in the coolant in the primary loop, so as to eliminate the influence of the lithium element on the nuclear reactivity of the reactor. And the independent boronizing is carried out for eliminating xenon poison in the coolant in the primary loop after the power of the nuclear power station unit is reduced. The independent dilution is to dilute the coolant in the primary circuit to reduce the boron concentration of the coolant in the primary circuit, thereby increasing the power of the nuclear power plant core or solving the problem that the coolant in the primary circuit is too cold in temperature. The automatic supply is realized by triggering the automatic operation supply of the REA system due to too little coolant in the primary loop of the nuclear power station, and automatically stopping the supply after the requirement is met.
When the REA system is not operating, the valve 3 is in a fully closed state. The safety state of the valve 3 is fully opened, namely the valve 3 is in an automatic fully opened state when the valve is in a power-off and gas-loss state, and the boron-containing coolant which weakens the nuclear reactor core reactivity can be injected into a primary circuit under the emergency condition, so that the safety of a nuclear power station is ensured.
The valve 3 has two control modes, one mode is that the valve is closed by ensuring that a gas source enters the valve cylinder through the electromagnetic valve. The other is that the valve adjusting module 1 automatically adjusts the opening degree of the valve 3 through a direct current signal of 4-20mA, wherein the maximum value of the opening degree of the valve 3 is 100%, and the minimum value is 0%. When the opening degree of the valve 3 is 100%, it means that the valve is fully opened, and when the opening degree of the valve 3 is 0%, it means that the valve is fully closed.
When the REA system is not in operation, an operator needs to convert the given boron flow value according to the boron concentration of the coolant in the primary loop, the conversion method is that the product of the boron concentration value of the coolant in the primary loop and a coefficient is divided by the difference between the boron concentration value of the coolant in the boron tank and the boron concentration value of the coolant in the primary loop, and the coefficient can be 10. For example, the following equation:
Figure BDA0001322876510000051
the given boron flow value is input into the valve regulating module 1 through the given value input device 2, and if the monitoring flow of the boron flow monitor 4 is zero, the given boron flow value is larger than the monitored boron flow value (hereinafter referred to as the monitoring value) of the boron flow monitor 4, so that the opening of the valve regulating module 1 for controlling the valve 3 is 100% of the maximum value.
When the REA system operates in any mode, such as manual supply, water change and the like, because the valve 3 is completely opened, the monitoring value is higher than the boron flow set value at the moment when the REA system just starts to operate, then the valve 3 gradually reduces the opening under the control of the valve adjusting module 1, so that the monitoring value gradually approaches the boron flow set value, and when the monitoring value reaches the boron flow set value, the system is closed to finish the automatic adjusting process.
If the actual boron flow of the primary loop is greater than the set boron flow value after the REA system is finished, the reactivity of the nuclear reactor core is weakened, and the primary loop of the nuclear power plant is cooled too much. In order to prevent the boron flow entering the primary circuit from being larger than a given boron flow value, when the coolant injection flow value injected into the primary circuit is larger than the given boron flow value and lasts for 30 seconds and is 0.3 liter/hour, a deviation alarm is triggered, and the valve adjusting module 1 controls the valve 3 to be closed.
If the actual boron flow of the primary loop is less than the set boron flow value after the REA system is finished, the reactivity of the nuclear reactor core is enhanced, and the primary loop of the nuclear power station is heated to a partial heat state. In order to prevent the boron flow entering the primary circuit from being smaller than the given boron flow, when the coolant injection flow value injected into the primary circuit is smaller than the difference between the given boron flow value and 0.3 liter/hour for 30 seconds in the operation process of the REA system, a deviation alarm is triggered, and the valve adjusting module 1 controls the valve 3 to be closed.
At the end of the service life of the nuclear power plant unit, the boron concentration of the coolant in the primary loop can be continuously reduced. When the REA system carries out primary circuit water change operation, the boron flow set value obtained by conversion is lower (the lowest time reaches 0.2 liter/hour) according to the boron flow set value conversion method. Under the normal condition, when the boron flow given value is less than 0.8 liter/hour, when the REA system starts to operate, the opening of the valve 3 controlled by the valve adjusting module 1 is 100% of the maximum value, and further the injection flow of the coolant injected into the loop is controlled to be 15 liters/hour, the monitoring value of the boron flow monitor 4 is instantly heightened and is far greater than the boron flow given value, so that the valve 3 controlled by the valve adjusting module 1 is rapidly reduced to 0% of the minimum value, at the moment, the monitoring value of the boron flow monitor 4 is far less than the boron flow given value, the valve 3 controlled by the valve adjusting module 1 is rapidly increased in opening, at the moment, the monitoring value of the boron flow monitor 4 is far greater than the boron flow given value, and the valve adjusting module 1 controls the valve 3 to rapidly reduce the opening. Therefore, the valve 3 can be subjected to constant amplitude oscillation regulation, namely the actual flow of boron entering a loop is far greater than the given boron flow value, so that the reactivity of the loop is overcooled, or the actual flow of boron entering the loop is far less than the given boron flow value, so that the reactivity of the loop is overheated. Therefore, the poor adjusting effect of the valve 3 directly influences the stability of the reactivity of the primary loop.
As shown in fig. 4, fig. 4 shows an operation curve diagram of the regulating effect of the valve when the minimum value of the opening of the valve 3 controlled by the valve regulating module 1 is 0%, wherein a line 1 is a curve of the opening of the valve 3, and a line 2 is a curve of the monitoring value of the boron flow monitor 4. When the boron flow rate is below 0.8L/h, the constant amplitude oscillation operation curve is formed. At the end of the service life of the unit, the given boron flow value obtained by changing water in the primary loop according to the given boron flow value conversion method is less than 0.8 liter/hour.
In order to solve the above problem, according to another embodiment of the present invention, when the given value of the boron flow is not greater than 0.8 l/h, the valve adjusting module 1 controls the minimum value of the opening of the valve 3 to be set to 5.9% from 0% originally, and further controls the injection flow rate of the coolant injected into the loop to be changed from 0 to 15 l/h to 0.1 to 15 l/h. Even if the actual boron flow rate is reduced to the minimum value of 0.1 liter/hour (the test data shows that the actual boron flow rate monitored by the boron flow rate monitor 4 can be stabilized at the minimum value of 0.1 liter/hour and can not be reduced, if the valve is continuously closed, the actual boron flow rate can be reduced to 0 at the moment), the opening instruction output to the valve 3 by the valve adjusting module 1 through the direct current signal is 5.9 percent, the lower limit instruction output by the valve adjusting module 1 is adjusted to 5.9 percent from the original 0 percent, so that the opening of the valve 3 is not reduced when the opening is reduced to 5.9 percent, thereby avoiding reducing the actual flow of boron to 0 liter/hour, saving the adjusting time of the valve adjusting module 1 for adjusting the opening of the valve 3 from 5.9 percent to 0 percent, and the valve is not closed to be closed completely, so that the problem of constant amplitude oscillation of the boron flow regulating valve of the REA system when the boron flow constant value is lower (less than 0.8m3/h) is solved fundamentally.
When the REA system starts to operate, the opening of the valve 3 controlled by the valve adjusting module 1 is 15 liters/hour at the maximum, the monitoring value of the boron flow monitor 4 is instantly increased and is far greater than the given value of the boron flow, so that the valve adjusting module 1 controls the PID output instruction of the boron flow adjusting valve 3 to rapidly reduce the opening to 5.9 percent, the PID output instruction is no longer 0 percent before modification, the actual boron flow is minimum reduced to 0.1 liters/hour instead of 0 liters/hour before modification, at the moment, the monitoring value of the boron flow monitor 4 is not far less than the given value of the boron flow, therefore, the valve adjusting module 1 controls the valve 3 to slowly increase the opening to the given value of the boron flow, the automatic adjusting process is completed, and the operation requirement of the REA system in the whole service life of the unit is met.
The opening of the valve control module 1, namely the output direct current signal control valve 3 of the PID regulator, is set to 5.9% from 0% originally, and a large number of tests verify that the value is a critical value for establishing the actual boron flow and needs to be obtained through tests according to different flow characteristics of the boron flow regulating valve of each unit.
As shown in fig. 5, fig. 5 shows an operation curve diagram of the regulating effect of the valve when the minimum value of the opening of the valve 3 controlled by the valve regulating module 1 is 5.9%, wherein a line 1 is a curve of the opening of the valve 3, and a line 2 is a curve of the monitoring value of the boron flow monitor 4. When the boron flow rate is set below 0.8 l/h, there is no constant amplitude oscillation operating curve like that shown in fig. 4.
As shown in fig. 6, which is a graph showing the operation of the valve adjustment effect after the implementation of the present invention, line 1 is a curve of the opening degree of the valve 3, and line 2 is a curve of the monitoring value of the boron flow monitor 4. All of these curves were obtained when the boron flow rate was set to 0.8 liter/hr or less. When the boron flow constant value is more than 0.2 liter/hour, the adjusting effect is achieved, and the requirements of the REA system operation at the end of the whole service life of the unit are completely met.
As shown in fig. 7, it is a graph showing the operation of the valve adjustment effect by the water change operation before the implementation of the present invention, where line 1 is a curve of the opening degree of the valve 3, and line 2 is a curve of the monitoring value of the boron flow monitor 4. The boron flow rate was set to 0.23 l/h, and since the boron flow rate was close to the minimum, the valve 3 was adjusted to hunting.
As shown in fig. 8, it is a running graph showing the regulating effect of the valve when the water change operation is performed after the implementation of the present invention, where line 1 is a curve of the opening degree of the valve 3, and line 2 is a curve of the monitoring value of the boron flow monitor 4. The boron flow rate is set to be 0.23 liter/hour, the adjustment is good, and the problem of oscillation adjustment under the condition of lower set value is solved.
The embodiment of the invention solves the problem that when the water is changed in the end of the service life of the primary circuit of the nuclear power station unit, the valve is subjected to constant amplitude oscillation adjustment, so that the primary circuit of the reactor is over-cooled and over-heated. The same problems of the same type of units of other nuclear power stations can be solved. The invention improves the safety and stability of the nuclear power reactor and makes great contribution to the safe and stable operation of the nuclear power station.
An embodiment of the present invention provides a boron concentration control method for a nuclear power plant, as shown in fig. 2, the method including the steps of:
s201: the boron concentration of the coolant in the circuit is measured.
S202: the boron concentration setpoint is calculated from the measured concentration.
The boron flow setpoint is a quotient of the product of the actual boron concentration in the circuit, which is the boron concentration in the circuit prior to injection of the coolant, and a coefficient divided by the difference between the boron concentration of the coolant in the boron tank and the actual boron concentration.
S203: the minimum value of the valve opening is set to 5.9%.
S204, a valve is opened, and the opening of the valve is controlled according to the comparison result of the boron flow in the coolant monitored by the boron flow monitor and the given boron flow value, so that the injection flow of the coolant injected into the loop is controlled.
S205: the boron flow monitor continuously measures the boron flow in the loop to obtain a monitoring value, and the monitoring value is the same as the given value of the boron flow.
S206: the valve is closed.
The operation method controls the opening of the valve, and further controls the injection flow of the coolant injected into the loop, so as to realize the boron concentration control of the coolant in the loop.
The present invention has been described in terms of specific examples, which are provided to aid understanding of the invention and are not intended to be limiting. For a person skilled in the art to which the invention pertains, several simple deductions, modifications or substitutions may be made according to the idea of the invention.

Claims (8)

1. A boron concentration control apparatus for a nuclear power plant, the boron concentration control apparatus being for controlling a boron concentration in a coolant in a primary circuit, characterized in that: the boron flow monitoring device comprises a boron flow monitor, a valve and a valve adjusting module;
the boron flow monitor is arranged in a loop and used for monitoring the boron flow of coolant in the loop;
the valve is arranged on a passage between the boron tank output pipeline and a primary circuit coolant injection port, the opening degree of the valve is adjustable, and the injection flow of the coolant injected into the primary circuit can be controlled by adjusting the opening degree;
the valve adjusting module is used for comparing the boron flow monitored by the boron flow monitor with a given boron flow value and controlling the opening of the valve according to a comparison result, wherein the minimum value of the opening of the valve is 0 percent, and the maximum value of the valve is 100 percent;
the boron flow setpoint is a quotient of a product of an actual boron concentration in a circuit, which is the boron concentration in the circuit prior to injection of coolant into the boron tank, and a coefficient divided by a difference between the actual boron concentration of coolant in the boron tank and the boron concentration;
the valve adjusting module outputs a direct current signal according to the comparison result, and the opening degree of the valve is controlled through the direct current signal;
and according to the percentage obtained by the quotient of the boron flow value monitored by the boron flow monitor and the boron flow set value, the valve adjusting module outputs a corresponding direct current signal to control the corresponding opening degree of the valve.
2. The boron concentration control apparatus of claim 1, wherein the valve adjustment module controls the minimum value of the opening of the valve to be 5.9%.
3. The boron concentration control apparatus according to claim 1, wherein the valve adjustment module outputs the direct current signal to control the opening of the valve to 0% when an injection flow rate of the coolant injected into the circuit is greater than a first value for a first predetermined period of time during operation of the boron concentration control apparatus, wherein the first value is a specific value greater than the given value of the boron flow rate.
4. The boron concentration control apparatus according to claim 1, wherein the valve adjustment module outputs the direct current signal to control the opening of the valve to 100% when an injection flow rate of the coolant injected into the circuit is less than a second value for a second predetermined period of time during operation of the boron concentration control apparatus, wherein the second value is a specific value less than the given value of the boron flow rate.
5. The boron concentration control apparatus according to claim 1, wherein the coolant is a mixed liquid of boron and water.
6. The boron concentration control apparatus according to claim 1, wherein the boron concentration in the coolant containing boron in the boron tank is 7000 μ g/g.
7. A boron concentration control method for a nuclear power plant, which is applied to the boron concentration control apparatus according to any one of claims 1 to 6, the boron concentration control method comprising the steps of:
measuring the boron flow of the coolant in the loop;
controlling the opening of a valve according to the comparison result of the boron flow in the coolant monitored by the boron flow monitor and a given boron flow value;
opening a valve according to the valve opening to control an injection flow rate of the coolant injected into the circuit;
the boron flow rate set point is a quotient of a product of an actual boron concentration of the coolant in the circuit before the coolant is injected into the boron tank and a coefficient divided by a difference between the actual boron concentration of the coolant containing boron in the boron tank and the actual boron concentration.
8. The boron concentration control method according to claim 7, wherein the minimum value of the opening degree of the valve is set to 5.9%.
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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP3732693A2 (en) * 2017-12-29 2020-11-04 NuScale Power, LLC Controlling a nuclear reaction
CN109887554B (en) * 2019-03-13 2021-10-22 广西防城港核电有限公司 Method for calculating critical dissolved boron content of nuclear reactor primary loop coolant
CN110096076B (en) * 2019-04-25 2022-08-12 岭东核电有限公司 Boron supply control circuit, equipment and method for million-kilowatt nuclear power station
CN112394639B (en) * 2020-11-20 2021-08-24 西安热工研究院有限公司 Nuclear power unit control rod adjusting method and system with incremental adjusting function
CN112858376B (en) * 2021-01-04 2023-12-29 广西防城港核电有限公司 Method for measuring content of dissolved hydrogen in primary loop of reactor

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03255399A (en) * 1990-03-05 1991-11-14 Mitsubishi Heavy Ind Ltd Controlling device of nuclear reactor output
JP2012083113A (en) * 2010-10-06 2012-04-26 Mitsubishi Heavy Ind Ltd Control device and control method
CN202887744U (en) * 2012-09-27 2013-04-17 中国核电工程有限公司 Combined active and passive emergency shut-down system

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4225390A (en) * 1970-01-14 1980-09-30 Westinghouse Electric Corp. Boron control system for a nuclear power plant
JPH05100069A (en) * 1991-05-07 1993-04-23 Hokkaido Electric Power Co Inc:The Boron concentration control system for light water cooled nuclear reactor
FR2747784B1 (en) * 1996-04-17 1998-07-24 Framatome Sa METHOD OF MEASURING THE LITHIUM CONCENTRATION OF THE COOLING WATER OF A NUCLEAR REACTOR
JP5364424B2 (en) * 2009-04-14 2013-12-11 三菱重工業株式会社 Reactor
CN102376374A (en) * 2010-08-26 2012-03-14 中国核动力研究设计院 Boron concentration online monitoring system for nuclear power station
CN103811084B (en) * 2012-11-14 2017-07-11 中国广核集团有限公司 A kind of nuclear power station residual heat removal system put into operation before preparation method
CN103871506B (en) * 2012-12-11 2016-12-21 中国核动力研究设计院 A kind of nuclear power station high-pressure safe injection system
CN104916340B (en) * 2014-03-12 2018-02-13 江苏核电有限公司 A kind of end of term in nuclear power station longevity reactivity control method
CN203895129U (en) * 2014-04-18 2014-10-22 中国核电工程有限公司 Reactor boric acid supplying system with emergency concentrated boric acid injection function
US10014081B2 (en) * 2015-11-01 2018-07-03 Daniel Lee Laughman Block-type movable reflector/moderator (RM) for nuclear reactor control

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH03255399A (en) * 1990-03-05 1991-11-14 Mitsubishi Heavy Ind Ltd Controlling device of nuclear reactor output
JP2012083113A (en) * 2010-10-06 2012-04-26 Mitsubishi Heavy Ind Ltd Control device and control method
CN202887744U (en) * 2012-09-27 2013-04-17 中国核电工程有限公司 Combined active and passive emergency shut-down system

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