WO2015186274A1 - Dispositif de commande d'alimentation en eau et dispositif d'alimentation en eau - Google Patents

Dispositif de commande d'alimentation en eau et dispositif d'alimentation en eau Download PDF

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Publication number
WO2015186274A1
WO2015186274A1 PCT/JP2014/080823 JP2014080823W WO2015186274A1 WO 2015186274 A1 WO2015186274 A1 WO 2015186274A1 JP 2014080823 W JP2014080823 W JP 2014080823W WO 2015186274 A1 WO2015186274 A1 WO 2015186274A1
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WIPO (PCT)
Prior art keywords
water supply
valve
steam generator
bypass
water
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PCT/JP2014/080823
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English (en)
Japanese (ja)
Inventor
健太 清水
明裕 柴田
昇 松井
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三菱重工業株式会社
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Publication of WO2015186274A1 publication Critical patent/WO2015186274A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/08—Regulation of any parameters in the plant
    • 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

Definitions

  • the present invention relates to a water supply control device and a water supply device for supplying a coolant to a steam generator provided in a nuclear facility.
  • a water supply device described in Patent Document 1 is provided in a water supply pipe connected to a steam generator and a water supply pipe in order to supply a coolant to a steam generator provided in a nuclear facility.
  • a water supply valve with a large rated capacity, a bypass pipe connected to the water supply pipe on the upstream side and the downstream side of the water supply valve, a bypass valve provided in the bypass pipe and having a smaller rated capacity than the water supply valve, and steam generation Based on the water level detection means provided so that the water level of the coolant in the vessel can be detected, and the water level deviation between the detected water level detected by the water level detection means and the preset target water level of the coolant in the steam generator
  • a water supply control device provided to control the water supply valve and the bypass valve so as to control the water supply flow rate of the coolant supplied to the steam generator.
  • This invention solves the subject mentioned above, and aims at providing the water supply control apparatus and water supply apparatus which can improve the responsiveness of control.
  • the water supply control device provides the secondary coolant by heat exchange between the secondary coolant in the steam generator and the primary coolant output from the reactor cooling system.
  • a water supply pipe connected to the steam generator so as to supply the secondary coolant to the steam generator, and a water supply valve provided in the water supply pipe in a nuclear facility that generates steam from
  • a water supply control device for controlling a water supply device comprising: a valve opening degree of the water supply valve based on an output state of a nuclear reactor.
  • the water supply valve is controlled with the valve opening degree according to the output state of the reactor as a target, the water level of the coolant in the steam generator is quickly set to the water level according to the output state of the reactor. You can get closer. As a result, the responsiveness of control can be improved.
  • the valve opening of the water supply valve is set based on the output state of the reactor, the influence of the reverse response of the coolant level in the steam generator can be reduced, and the time required for adjustment can be shortened. .
  • the water supply control device is the water supply control device according to the first invention, wherein the water level of the secondary coolant in the steam generator, the water supply flow rate of the secondary coolant in the water supply pipe, and the steam generation
  • the valve opening degree of the water supply valve is adjusted based on the steam flow rate of the steam flowing out from the vessel.
  • the water supply valve is controlled with the valve opening degree according to the output state of the reactor as a target, and in addition to this control, the water level of the coolant in the steam generator and the coolant level in the water supply pipe are controlled.
  • the valve opening of the water supply valve based on the water supply flow rate and the steam flow rate of the steam flowing out of the steam generator, the water supply valve is adjusted to a more suitable valve opening according to the state in the steam generator. Can be controlled.
  • the water supply control device is the water supply control device according to the first or second invention, wherein the water supply device includes a bypass pipe connected to the water supply pipe on an upstream side and a downstream side of the water supply valve, and the bypass A bypass valve that is provided in a pipe and has a smaller rated capacity than the water supply valve, and sets the valve opening of the bypass valve based on the output state of the reactor, and the steam generator The valve opening degree of the bypass valve is adjusted based on the water level of the secondary coolant in the inside.
  • the water level of the coolant in the steam generator is controlled in the reactor in order to control the bypass valve with the valve opening degree according to the output state of the reactor as a target. It is possible to quickly approach the water level according to the output state. As a result, the responsiveness of control can be improved.
  • the valve opening of the bypass valve is set based on the output state of the reactor, the influence of the response delay of the steam generator water level at the time of low output can be reduced, and the time required for adjustment can be shortened.
  • bypass valve By controlling the bypass valve with the valve opening according to the output state of the reactor as a target, and adjusting the valve opening of the bypass valve based on the coolant level in the steam generator in addition to this control Even if the Cv value characteristic of the bypass valve differs from the design due to manufacturing errors, the bypass valve can be controlled to a more suitable valve opening according to the state of the steam generator.
  • the water supply control device is the water supply control device according to the first or second aspect, wherein the water supply device includes a bypass pipe connected to the water supply pipe on the upstream side and the downstream side of the water supply valve, and the bypass A bypass valve that is provided in a pipe and has a smaller rated capacity than the water supply valve, and sets the valve opening of the bypass valve based on the output state of the reactor, and the steam generator The valve opening degree of the bypass valve is adjusted based on the water level of the secondary coolant in the inside and the feed water flow rate obtained corresponding to the capacity of the bypass valve.
  • the water level of the coolant in the steam generator is controlled in the reactor in order to control the bypass valve with the valve opening degree according to the output state of the reactor as a target. It is possible to quickly approach the water level according to the output state. As a result, the responsiveness of control can be improved.
  • the valve opening of the bypass valve is set based on the output state of the reactor, the influence of the response delay of the steam generator water level at the time of low output can be reduced, and the time required for adjustment can be shortened.
  • the bypass valve is controlled with the valve opening according to the output state of the reactor as a target, and in addition to this control, based on the coolant level in the steam generator and the coolant flow rate in the bypass pipe
  • the valve opening degree of the bypass valve By adjusting the valve opening degree of the bypass valve, even if the Cv value characteristic of the bypass valve differs from the design due to manufacturing errors, etc., a more suitable valve according to the state of the steam generator
  • the bypass valve can be controlled to the opening degree.
  • a water supply apparatus provides the water supply device of the steam generator by heat exchange between the secondary coolant in the steam generator and the primary coolant output from the reactor cooling system.
  • a water supply pipe connected to the steam generator so as to supply the secondary coolant toward the steam generator in a nuclear facility that generates steam from the secondary coolant, and provided in the water supply pipe
  • a water supply control device according to any one of the first to fourth inventions for controlling the valve and the bypass valve.
  • the water level of the coolant in the steam generator is controlled according to the output state of the reactor by controlling the water supply valve and the bypass valve with the valve opening degree corresponding to the output state of the reactor as a target.
  • the water level can be approached quickly.
  • the responsiveness of control can be improved.
  • the valve opening of the water supply valve and bypass valve is set based on the reactor power state, the water level of the coolant in the steam generator is reversed, and the steam generator is cooled at low power.
  • the influence of the response delay of the water level of the material can be reduced, and the time required for adjustment can be shortened.
  • the responsiveness of control can be improved.
  • FIG. 1 is a schematic configuration diagram of a nuclear facility provided with a water supply apparatus according to an embodiment of the present invention.
  • FIG. 2 is a control block diagram relating to a water supply system in the water supply control device according to the embodiment of the present invention.
  • FIG. 3 is a graph showing control related to the water supply system in the water supply control device according to the embodiment of the present invention.
  • FIG. 4 is a control block diagram relating to a water supply bypass system in the water supply control device according to the embodiment of the present invention.
  • FIG. 5 is another control block diagram relating to a water supply bypass system in the water supply control device according to the embodiment of the present invention.
  • FIG. 1 is a schematic configuration diagram of a nuclear facility equipped with a water supply apparatus according to the present embodiment.
  • the nuclear facility 1 has a nuclear reactor 2.
  • a reactor cooling system primary cooling system
  • a turbine system secondary cooling system 200 that exchanges heat with the reactor cooling system 100. It consists of.
  • a primary coolant flows, and in the turbine system 200, a secondary coolant flows.
  • the reactor cooling system 100 has a steam generator 4 connected to the reactor 2 via a cold leg 3a and a hot leg 3b.
  • the hot leg 3b is provided with a pressurizer 5, and the cold leg 3a is provided with a primary coolant pump 6.
  • the reactor 2, the cold leg 3 a, the hot leg 3 b, the steam generator 4, the pressurizer 5, and the primary coolant pump 6 are accommodated in the reactor containment vessel 7.
  • Reactor 2 is a pressurized water reactor as described above, and its interior is filled with a primary coolant.
  • the primary coolant is light water in which boron used as a neutron moderator is dissolved.
  • the nuclear reactor 2 contains a large number of fuel assemblies 8 therein, and a large number of control rods 9 for controlling the nuclear fission of the fuel assemblies 8 are removably provided in the fuel assemblies 8. ing.
  • the high-temperature and high-pressure primary coolant flowing into the steam generator 4 is cooled by exchanging heat with the secondary coolant, and the cooled primary coolant is passed through the cold leg 3a by the primary coolant pump 6 to the nuclear reactor. Sent to 2. Then, the cooled primary coolant flows into the reactor 2, so that the reactor 2 is cooled. Thus, the primary coolant circulates between the nuclear reactor 2 and the steam generator 4.
  • the turbine system 200 includes a turbine 12 connected to the steam generator 4 via the steam pipe 11, a condenser 13 connected to the turbine 12, and a water supply pipe 14 connecting the condenser 13 and the steam generator 4. A water supply pump 15 interposed between the two.
  • the turbine 12 is connected to a generator 16.
  • a series of operations in the turbine system 200 of the nuclear facility 1 will be described.
  • the turbine 12 rotates.
  • the generator 16 connected to the turbine 12 generates power.
  • the steam flowing out of the turbine 12 flows into the condenser 13.
  • the condenser 13 has a cooling pipe 17 disposed therein, and one of the cooling pipes 17 is connected to a water intake pipe 18 for supplying cooling water (for example, seawater).
  • a drain pipe 19 for draining the cooling water is connected to.
  • the condenser 13 cools the steam flowing in from the turbine 12 by the cooling pipe 17, thereby returning the steam to a liquid.
  • the secondary coolant that has become liquid is sent to the steam generator 4 via the water supply pipe 14 by the water supply pump 15.
  • the secondary coolant sent to the steam generator 4 becomes steam again by exchanging heat with the primary coolant in the steam generator 4.
  • the secondary coolant is supplied toward the steam generator 4 while the flow rate is controlled by the water supply device 40 including the water supply pipe 14 and the water supply pump 15.
  • the water supply device 40 is connected to the water supply pipe 14 by bypassing the water supply pipe 14, the water supply pump 15, the water supply valve 42 provided in the water supply pipe 14, and the water supply valve 42.
  • a temperature sensor 49 and a second temperature sensor 50 provided in the hot leg 3b are provided.
  • the water supply device 40 is controlled by a water supply control device 51.
  • the water supply valve 42 is provided on the downstream side of the water supply pump 15 in the water supply pipe 14.
  • the water supply valve 42 is a pneumatic control valve and has a larger rated capacity than the bypass valve 44.
  • One end of the bypass pipe 43 is connected to the water supply pipe 14 on the upstream side of the water supply valve 42, and the other end is connected to the water supply pipe 14 on the downstream side of the water supply valve 42.
  • the bypass valve 44 is provided in the bypass pipe 43.
  • the bypass valve 44 is a pneumatic control valve similar to the water supply valve 42, but has a smaller rated capacity than the water supply valve 42.
  • the water level gauge 45 is provided in the steam generator 4 and measures the water level of the secondary coolant in the steam generator 4.
  • the water supply flow meter 46 is provided in the water supply pipe 14 on the downstream side of the water supply valve 42, and measures the flow rate of the liquid phase secondary coolant flowing in the water supply pipe 14. This water supply flow meter 46 corresponds to the capacity of the water supply valve 42 and measures the water supply flow rate in the secondary coolant flowing through the water supply valve 42.
  • the steam flow meter 47 measures the steam flow rate in the steam (gas phase secondary coolant) flowing in the steam pipe 11.
  • the feed water bypass flow meter 48 is provided in the bypass pipe 43 or the feed water pipe 14 on the downstream side of the bypass valve 44 and measures the flow rate of the liquid phase secondary coolant flowing in the feed water pipe 14.
  • This water supply bypass flow meter 48 corresponds to the capacity of the bypass valve 44 and measures the narrow area water supply flow rate in the secondary coolant flowing through the bypass valve 44.
  • the first temperature sensor 49 detects the temperature of the primary coolant flowing through the cold leg 3a.
  • the second temperature sensor 50 detects the temperature of the primary coolant flowing through the hot leg 3b.
  • the water supply control device 51 controls the water supply device 40 in an integrated manner.
  • the water supply control device 51 is connected to a water level meter 45, a water supply flow meter 46, a steam flow meter 47, a water supply bypass flow meter 48, a first temperature sensor 49, and a second temperature sensor 50, and further includes a water supply valve 42 and a bypass valve. 44.
  • the water supply control device 51 includes a water supply valve 42 and a bypass based on inputs from a water level meter 45, a water supply flow meter 46, a steam flow meter 47, a water supply bypass flow meter 48, a first temperature sensor 49, and a second temperature sensor 50. By controlling the valve 44, the water supply to the steam generator 4 is controlled.
  • FIG. 2 is a control block diagram relating to the water supply system in the water supply control device according to the present embodiment.
  • FIG. 3 is a graph which shows the control regarding the water supply system in the water supply control apparatus which concerns on this embodiment.
  • 4 and 5 are control block diagrams relating to a water supply bypass system in the water supply control device according to the present embodiment.
  • the water supply system means water supply control in which the water supply control device 51 controls the water supply valve 42 in the open state and does not control the bypass valve 44 in the closed state.
  • the water supply bypass system means water supply control in which the water supply control device 51 controls the bypass valve 44 in an open state and does not control the water supply valve 42 in a closed state.
  • the water supply control device 51 includes a first water level setting unit 52, a first variable gain setting unit 53, a first PI control unit (first feedback control unit) 54, A two-variable gain setting unit 55, a second PI control unit (second feedback control unit) 56, and a first valve opening signal output unit 57 are provided.
  • the first water level setting unit 52 sets the target water level in the steam generator 4 according to the steam pressure around the first stage stationary blade that is around the inlet of the turbine 12 [turbine first stage pressure].
  • the water level set value is set based on the graph G1 shown in FIG.
  • the graph G1 is predetermined, the horizontal axis is the turbine first stage pressure, and the vertical axis is the water level set value. For this reason, when the turbine first stage pressure signal is input, the water supply control device 51 derives the water level set value based on the turbine first stage pressure and the graph G1 of the first water level setting unit 52.
  • the first variable gain setting unit 53 sets a variable first proportional gain.
  • the magnitude of the first proportional gain is set based on the temperature difference ⁇ T between the temperature of the cold leg 3 a obtained by the first temperature sensor 49 and the temperature of the hot leg 3 b obtained by the second temperature sensor 50.
  • This temperature difference ⁇ T is derived by the feed water control device 51 based on inputs from the first temperature sensor 49 and the second temperature sensor 50 and is an index of the output of the nuclear reactor 2.
  • the water supply control device 51 derives the first proportional gain from the graph G2 shown in FIG. 2 based on the derived temperature difference ⁇ T.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the first proportional gain.
  • the first proportional gain is a preset lower limit proportional gain when the temperature difference ⁇ T is from 0 to T1, and from T1 to T2, the lower limit proportional gain is set to the preset upper limit proportional gain. Up to T2 and above is the upper limit proportional gain.
  • the first PI control unit 54 is connected to the output side of the first variable gain setting unit 53.
  • the first PI control unit 54 performs feedback control (PI control) on the control input signal by performing proportional control using the first proportional gain and integral control on the control input signal IS1 that is the water level deviation. Then, the first PI control unit 54 outputs the control input signal after the PI control as a control output signal (first control output signal) OS1.
  • PI control feedback control
  • the second variable gain setting unit 55 has a first PI control unit 54, a feed water flow meter 46, and a steam flow meter 47 connected to its input side, and a second PI control unit 56 connected to its output side. Then, the second variable gain setting unit 55 sets a variable second proportional gain.
  • the magnitude of the second proportional gain is the control value of the derived signal derived from the control output signal OS1 output from the first PI controller 54 and the control input signal (second control input signal) IS2 that is a flow rate deviation.
  • the control value of the derived signal is a deviation value in consideration of the water level deviation after PI control, which is the control output signal OS1 output from the first PI control unit 54, and the flow rate deviation, which is the control input signal IS2. .
  • the water supply control device 51 derives the second proportional gain from the graph G3 shown in FIG. 2 based on the control value of the derived signal.
  • the horizontal axis represents the control value of the derived signal
  • the vertical axis represents the second proportional gain.
  • the second proportional gain is a preset lower limit proportional gain when the control value is 0, that is, when the deviation is 0.
  • the second proportional gain increases from a lower limit proportional gain to a preset upper limit proportional gain when the control value is from 0 to S1, and when the control value is larger than S1, the second proportional gain is an upper limit proportional gain.
  • the second proportional gain increases from the lower limit proportional gain to a preset upper limit proportional gain when the control value is from 0 to -S1, and is the upper limit proportional gain when the control value is smaller than -S1.
  • the second PI control unit 56 is connected to the output side of the second variable gain setting unit 55.
  • the second PI control unit 56 performs feedback control (PI control) on the derived signal by performing proportional control using the second proportional gain and integral control on the derived signal. Then, the second PI control unit 56 outputs the derived signal after the PI control as a control output signal (second control output signal) OS2 for controlling the water supply valve 42.
  • PI control feedback control
  • the first valve opening signal output unit 57 is a control output signal (third control output signal) OS3 for controlling the valve opening of the water supply valve 42 based on the temperature difference ⁇ T that is an index of the output of the reactor 2.
  • the water supply control device 51 derives the valve opening degree of the water supply valve 42 from the graph G4 shown in FIG. 2 based on the derived temperature difference ⁇ T.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the valve opening.
  • the water supply control device 51 controls the water supply valve 42 by combining the control output signal OS3 output from the first valve opening signal output unit 57 and the control output signal OS2 output from the second PI control unit 56.
  • An output signal (fourth control output signal) OS4 is output. That is, the water supply control device 51 outputs the control output signal OS3 of the valve opening of the water supply valve 42 based on the temperature difference ⁇ T that is the output state of the reactor 2 from the first valve opening signal output unit 57. As shown by a broken line in FIG. 3, the valve opening degree of the water supply valve 42, which is a target value, is set.
  • the water supply control apparatus 51 outputs this control output signal OS3 to the water supply valve 42, and controls the valve opening degree of the water supply valve 42 to a target value as shown by a solid line in FIG.
  • the feed water control device 51 is based on the water level of the secondary coolant in the steam generator 4, the feed water flow rate of the secondary coolant in the feed water pipe 14, and the steam flow rate of the steam flowing out of the steam generator 4.
  • the valve opening degree of the water supply valve 42 is adjusted as shown by the solid line in FIG. That is, in consideration of the water level that can be changed by the output of the reactor 2 until the valve opening degree of the water supply valve 42 is controlled to the target value (range shown by hatching in FIG. 3), this is added and adjusted.
  • 3 indicates the water supply control when the control output signal OS3 output from the first valve opening signal output unit 57 is not used.
  • the water supply control device 51 includes a second water level setting unit 62, a third variable gain setting unit 63, and a second valve opening signal output unit 64, as shown in FIG. Yes.
  • the second water level setting unit 62 sets the target water level in the steam generator 4 according to the steam pressure around the first stage stationary blade that is around the inlet of the turbine 12 [turbine first stage pressure].
  • the water level set value is set based on the graph G5 shown in FIG.
  • the graph G5 is predetermined, the horizontal axis is the turbine first stage pressure, and the vertical axis is the water level set value. For this reason, when the turbine first stage pressure signal is input, the water supply control device 51 derives the water level set value based on the turbine first stage pressure and the graph G5 of the water level setting unit 62.
  • the third variable gain setting unit 63 sets a variable third proportional gain.
  • the magnitude of the third proportional gain is set based on the temperature difference ⁇ T between the temperature of the cold leg 3 a obtained by the first temperature sensor 49 and the temperature of the hot leg 3 b obtained by the second temperature sensor 50.
  • This temperature difference ⁇ T is derived by the feed water control device 51 based on inputs from the first temperature sensor 49 and the second temperature sensor 50 and is an index of the output of the nuclear reactor 2.
  • the water supply control device 51 derives the third proportional gain from the graph G6 shown in FIG. 4 based on the derived temperature difference ⁇ T.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the third proportional gain.
  • the third proportional gain is a preset upper limit proportional gain from a preset lower limit proportional gain KL until the temperature difference ⁇ T is 0 to 20% (corresponding to an output region in which the bypass valve 44 is used). It increases to KH, and 20% or more is the upper limit proportional gain KH.
  • the second valve opening signal output unit 64 is a control output signal (fifth control output signal) OS5 for controlling the valve opening of the bypass valve 44 based on the temperature difference ⁇ T that is an index of the output of the reactor 2.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the valve opening.
  • the water supply control device 51 uses the control output signal OS5 output from the second valve opening signal output unit 64 and the third proportional gain of the third variable gain setting unit 63 to control the bypass valve 44.
  • a signal (sixth control output signal) OS6 is output. That is, the water supply control device 51 outputs a control output signal OS5 of the valve opening degree of the bypass valve 44 based on the temperature difference ⁇ T that is an index of the output of the nuclear reactor 2 from the second valve opening degree signal output unit 64. Then, the valve opening degree of the bypass valve 44 which is a target value is set. And the water supply control apparatus 51 outputs this control output signal OS5 to the bypass valve 44, for example, controls the valve opening degree of the bypass valve 44 to a target value, as shown by the continuous line in FIG.
  • the water supply control device 51 adjusts the valve opening degree of the bypass valve 44 based on the water level of the secondary coolant in the steam generator 4, for example, as shown by a solid line in FIG. That is, in consideration of the water level that can be reduced by the output of the reactor 2 until the valve opening degree of the bypass valve 44 is controlled to the target value (for example, the range shown by hatching in FIG. 3), this is added and adjusted.
  • . 3 corresponds to the water supply control in the case where the control output signal OS5 output from the second valve opening signal output unit 64 is not used.
  • the water supply control device 51 in addition to the second water level setting unit 62, the third variable gain setting unit 63, and the second valve opening signal output unit 64, as shown in FIG.
  • the third PI control unit (third feedback control unit) 65, the steam flow signal output unit 66, and the fourth PI control unit (third feedback control unit) 67 may be included.
  • the second water level setting unit 62 sets the target water level in the steam generator 4 according to the steam pressure around the first stage stationary blade that is around the inlet of the turbine 12 [turbine first stage pressure].
  • the water level set value is set based on the graph G5 shown in FIG.
  • the graph G5 is predetermined, the horizontal axis is the turbine first stage pressure, and the vertical axis is the water level set value. For this reason, when the turbine first stage pressure signal is input, the water supply control device 51 derives the water level set value based on the turbine first stage pressure and the graph G5 of the second water level setting unit 62.
  • the third variable gain setting unit 63 sets a variable third proportional gain.
  • the magnitude of the third proportional gain is set based on the temperature difference ⁇ T between the temperature of the cold leg 3 a obtained by the first temperature sensor 49 and the temperature of the hot leg 3 b obtained by the second temperature sensor 50.
  • This temperature difference ⁇ T is derived by the feed water control device 51 based on inputs from the first temperature sensor 49 and the second temperature sensor 50 and is an index of the output of the nuclear reactor 2.
  • the water supply control device 51 derives a third proportional gain from the graph G6 shown in FIG. 5 based on the derived temperature difference ⁇ T.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the third proportional gain.
  • the third proportional gain is a preset upper limit proportional gain from a preset lower limit proportional gain KL until the temperature difference ⁇ T is 0 to 20% (corresponding to an output region in which the bypass valve 44 is used). It increases to KH, and 20% or more is the upper limit proportional gain KH.
  • the third PI control unit 65 is connected to the output side of the third variable gain setting unit 63.
  • the third PI control unit 65 performs feedback control (PI control) on the derived signal by performing proportional control using the third proportional gain and integral control on the derived signal. Then, the third PI control unit 65 outputs the control input signal after PI control as a control output signal (seventh control output signal) OS7.
  • PI control feedback control
  • the steam flow signal output unit 66 outputs a control output signal (eighth control output signal) OS8 that is a flow rate of steam flowing out of the steam generator 4 based on the temperature difference ⁇ T that is an index of the output of the reactor 2. That is, the water supply control device 51 derives the steam flow rate of the steam generator 4 from the graph G8 shown in FIG. 5 based on the derived temperature difference ⁇ T.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the steam flow rate.
  • the fourth PI controller 67 is connected to the output side of the third PI controller 65 and the steam flow signal output unit 66.
  • the fourth PI controller 67 controls the third PI controller 65 with respect to the flow rate deviation between the narrow area water supply flow detected by the water supply bypass flow meter 48 and the steam flow output from the steam flow signal output unit 66.
  • the control input signal is feedback-controlled (PI control).
  • the fourth PI control unit 67 then outputs the control input signal after PI control as a control output signal (ninth control output signal) OS9 for controlling the bypass valve 44.
  • the second valve opening signal output unit 64 is a control output signal (fifth control output signal) OS5 for controlling the valve opening of the bypass valve 44 based on the temperature difference ⁇ T that is an index of the output of the reactor 2.
  • the horizontal axis represents the temperature difference ⁇ T
  • the vertical axis represents the valve opening.
  • the water supply control device 51 controls the bypass valve 44 by combining the control output signal OS5 output from the second valve opening signal output unit 64 and the control output signal OS9 output from the fourth PI control unit 67.
  • An output signal (tenth control output signal) OS10 is output. That is, the water supply control device 51 outputs a control output signal OS5 of the valve opening degree of the bypass valve 44 based on the temperature difference ⁇ T that is an index of the output of the nuclear reactor 2 from the second valve opening degree signal output unit 64.
  • the valve opening of the bypass valve 44 which is a target value, is set as shown by a broken line in FIG.
  • the water supply control apparatus 51 outputs this control output signal OS5 to the bypass valve 44, for example, controls the valve opening degree of the bypass valve 44 to a target value, as shown by the continuous line in FIG. Further, the feed water control device 51 outputs the water level of the secondary coolant in the steam generator 4, the narrow area feed water flow rate of the secondary coolant in the bypass pipe 43 or the feed water pipe 14, and the steam flow signal output unit 66. By outputting a control output signal OS9 based on the steam flow rate, the valve opening degree of the bypass valve 44 is adjusted as shown by a solid line in FIG.
  • . 3 corresponds to the water supply control in the case where the control output signal OS5 output from the second valve opening signal output unit 64 is not used.
  • the water supply control device 51 of this embodiment is configured so that the secondary coolant of the steam generator 4 is exchanged by heat exchange between the secondary coolant of the steam generator 4 and the primary coolant output from the reactor cooling system 100.
  • a water supply pipe 14 connected to the steam generator 4 so as to supply a secondary coolant to the steam generator 4 and water supply provided in the water supply pipe 14
  • the valve opening of the water supply valve 42 is set based on the output state of the nuclear reactor 2.
  • the output state of the reactor 2 index of the output of the reactor 2
  • the temperature of the primary coolant output from the reactor cooling system 100 and the steam generator 4 Based on the temperature difference ⁇ T with the temperature of the primary coolant that is cooled by heat exchange with the secondary coolant (coolant) and sent to the reactor 2
  • the valve opening according to the output state of the reactor 2 is By controlling the water supply valve 42 as a target, the water level of the secondary coolant in the steam generator 4 can be quickly brought close to the water level according to the output state of the reactor 2. As a result, the responsiveness of control can be improved.
  • valve opening of the water supply valve 42 is set based on the output state of the nuclear reactor 2, the influence of the reverse response of the water level of the secondary coolant in the steam generator 4 can be reduced, and the adjustment can be made. The time required can be shortened.
  • the water supply control device 51 of the present embodiment includes the water level of the secondary coolant in the steam generator 4, the feed water flow rate of the secondary coolant in the feed water pipe 14, and the steam flow rate of the steam flowing out from the steam generator 4. Based on the above, the valve opening degree of the water supply valve 42 is adjusted.
  • the water supply valve 42 is controlled with the valve opening according to the output state of the reactor 2 as a target, and in addition to this control, the water level of the secondary coolant in the steam generator 4, By adjusting the valve opening degree of the feed water valve 42 based on the feed water flow rate of the secondary coolant in the feed water pipe 14 and the steam flow rate of the steam flowing out from the steam generator 4, the state in the steam generator 4 is obtained. Accordingly, the water supply valve 42 can be controlled to a more suitable valve opening.
  • the water supply device 40 includes a bypass pipe 43 connected to the water supply pipe 14 on the upstream side and the downstream side of the water supply valve 42, and the water supply valve 42 provided on the bypass pipe 43. And a bypass valve 44 having a smaller rated capacity than that of the reactor.
  • the valve opening degree of the bypass valve 44 is set based on the output state of the nuclear reactor 2, and the secondary coolant in the steam generator 4 is set.
  • the valve opening degree of the bypass valve 44 is adjusted based on the water level.
  • this water supply control device 51 even in the water supply from the bypass pipe 43 side, the output state of the reactor 2, specifically, the temperature of the primary coolant output from the reactor cooling system 100, the steam generator 4, based on the temperature difference ⁇ T with the temperature of the primary coolant that is cooled by heat exchange with the secondary coolant and sent to the reactor 2, the valve opening according to the output state of the reactor 2 is bypassed as a target
  • the valve 44 By controlling the valve 44, the water level of the secondary coolant in the steam generator 4 can be quickly brought close to the water level according to the output state of the reactor 2. As a result, the responsiveness of control can be improved.
  • the opening degree of the bypass valve 44 is set based on the output state of the nuclear reactor 2, it is possible to reduce the influence of the response delay at the time of low output of the water level of the secondary coolant in the steam generator 4. And the time required for adjustment can be shortened. Then, the bypass valve 44 is controlled with the valve opening according to the output state of the reactor 2 as a target, and in addition to this control, the bypass valve 44 is opened based on the water level of the secondary coolant in the steam generator 4. By adjusting the degree, even if the Cv value characteristics of the bypass valve 44 differ from the design due to manufacturing errors, etc., the valve opening degree is more suitable for the state of the steam generator 4. The valve 44 can be controlled.
  • the water supply device 40 includes a bypass pipe 43 connected to the water supply pipe 14 on the upstream side and the downstream side of the water supply valve 42, and the water supply valve 42 provided on the bypass pipe 43. And a bypass valve 44 having a smaller rated capacity than that of the reactor.
  • the valve opening degree of the bypass valve 44 is set based on the output state of the nuclear reactor 2, and the secondary coolant in the steam generator 4 is set.
  • the valve opening degree of the bypass valve 44 is adjusted based on the water level and the feed water flow rate obtained corresponding to the capacity of the bypass valve 44.
  • this water supply control device 51 even in the water supply from the bypass pipe 43 side, the output state of the reactor 2, specifically, the temperature of the primary coolant output from the reactor cooling system 100, the steam generator 4, based on the temperature difference ⁇ T with the temperature of the primary coolant that is cooled by heat exchange with the secondary coolant and sent to the reactor 2, the valve opening according to the output state of the reactor 2 is bypassed as a target
  • the valve 44 By controlling the valve 44, the water level of the secondary coolant in the steam generator 4 can be quickly brought close to the water level according to the output state of the reactor 2. As a result, the responsiveness of control can be improved.
  • the opening degree of the bypass valve 44 is set based on the output state of the nuclear reactor 2, it is possible to reduce the influence of the response delay at the time of low output of the water level of the secondary coolant in the steam generator 4. And the time required for adjustment can be shortened. Then, the bypass valve 44 is controlled with the valve opening according to the output state of the reactor 2 as a target. In addition to this control, the water level of the secondary coolant in the steam generator 4 and the secondary cooling in the bypass pipe 43 are controlled. By adjusting the valve opening degree of the bypass valve 44 based on the feed water flow rate of the material, even if the Cv value characteristic of the bypass valve 44 is different from the design due to manufacturing errors, steam is generated. The bypass valve 44 can be controlled to a more suitable valve opening according to the state of the vessel 4.
  • the water supply device 40 of the present embodiment generates steam from the secondary coolant of the steam generator 4 by heat exchange between the secondary coolant of the steam generator 4 and the primary coolant output from the reactor cooling system 100.
  • a water supply pipe 14 connected to the steam generator 4 so as to supply a secondary coolant to the steam generator 4, a water supply valve 42 provided in the water supply pipe 14, and a water supply A bypass pipe 43 connected to the water supply pipe 14 on the upstream side and the downstream side of the valve 42, a bypass valve 44 provided in the bypass pipe 43 and having a smaller rated capacity than the water supply valve 42, the water supply valve 42 and the bypass A water supply control device 51 for controlling the valve 44.
  • the water level of the secondary coolant in the steam generator 4 is controlled by controlling the water supply valve 42 and the bypass valve 44 with the valve opening according to the output state of the reactor 2 as a target.
  • the water level corresponding to the output state of the furnace 2 can be quickly approached.
  • the responsiveness of control can be improved.
  • the valve opening degree of the water supply valve 42 and the bypass valve 44 is set based on the output state of the nuclear reactor 2, the reverse response of the water level of the secondary coolant in the steam generator 4 and at the time of low output The influence of the response delay of the coolant level in the steam generator can be reduced, and the time required for adjustment can be shortened.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

　La présente invention améliore la réactivité de commande. Plus particulièrement, la présente invention concerne un dispositif de commande d'alimentation en eau (51) conçu pour commander un dispositif d'alimentation en eau (40) dans une centrale nucléaire (1) où de la vapeur est générée à partir d'un fluide secondaire de refroidissement dans une unité de génération de vapeur (4) grâce à un échange de chaleur entre le fluide secondaire de refroidissement dans ladite unité de génération de vapeur (4) et un fluide primaire de refroidissement émis par un système de refroidissement de réacteur nucléaire (100). Le dispositif d'alimentation en eau (40) est pourvu d'un tuyau d'alimentation en eau (14) relié à un élément de génération de vapeur (4), de façon à alimenter cette unité de génération de vapeur (4) en fluide secondaire de refroidissement, et d'une vanne d'alimentation en eau (42) prévue dans le tuyau d'alimentation en eau (14). Le degré d'ouverture de la vanne d'alimentation en eau (42) est fixé sur la base de l'état de sortie d'un réacteur nucléaire (2).
PCT/JP2014/080823 2014-06-04 2014-11-20 Dispositif de commande d'alimentation en eau et dispositif d'alimentation en eau WO2015186274A1 (fr)

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JP2014116232A JP6553847B2 (ja) 2014-06-04 2014-06-04 給水制御装置および給水装置
JP2014-116232 2014-06-04

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112435765A (zh) * 2020-11-23 2021-03-02 华能山东石岛湾核电有限公司 一种高温气冷堆蒸汽发生器小流量冷却系统及控制方法

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS53102495A (en) * 1977-02-07 1978-09-06 Westinghouse Electric Corp Feed water controller for nuclear power plant
JPS5517091A (en) * 1978-05-25 1980-02-06 Framatome Sa Water level controlling method within boiler or steam generator
JPS57158596A (en) * 1981-03-02 1982-09-30 Westinghouse Electric Corp Method and device for generating electric power
JPH03504413A (ja) * 1988-04-14 1991-09-26 コンバッション　エンヂニアリング　インコーポレーテッド 低出力時の自動蒸気発生器制御
JPH04148101A (ja) * 1990-10-12 1992-05-21 Power Reactor & Nuclear Fuel Dev Corp 給水調節弁切替時の蒸気ドラム水位制御方法
JP2012047501A (ja) * 2010-08-24 2012-03-08 Mitsubishi Heavy Ind Ltd 給水装置

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS53102495A (en) * 1977-02-07 1978-09-06 Westinghouse Electric Corp Feed water controller for nuclear power plant
JPS5517091A (en) * 1978-05-25 1980-02-06 Framatome Sa Water level controlling method within boiler or steam generator
JPS57158596A (en) * 1981-03-02 1982-09-30 Westinghouse Electric Corp Method and device for generating electric power
JPH03504413A (ja) * 1988-04-14 1991-09-26 コンバッション　エンヂニアリング　インコーポレーテッド 低出力時の自動蒸気発生器制御
JPH04148101A (ja) * 1990-10-12 1992-05-21 Power Reactor & Nuclear Fuel Dev Corp 給水調節弁切替時の蒸気ドラム水位制御方法
JP2012047501A (ja) * 2010-08-24 2012-03-08 Mitsubishi Heavy Ind Ltd 給水装置

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112435765A (zh) * 2020-11-23 2021-03-02 华能山东石岛湾核电有限公司 一种高温气冷堆蒸汽发生器小流量冷却系统及控制方法

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