JP2017194312A5 - - Google Patents
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- JP2017194312A5 JP2017194312A5 JP2016083756A JP2016083756A JP2017194312A5 JP 2017194312 A5 JP2017194312 A5 JP 2017194312A5 JP 2016083756 A JP2016083756 A JP 2016083756A JP 2016083756 A JP2016083756 A JP 2016083756A JP 2017194312 A5 JP2017194312 A5 JP 2017194312A5
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- 238000000605 extraction Methods 0.000 claims 34
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims 21
- 238000000034 method Methods 0.000 claims 14
- 230000001276 controlling effect Effects 0.000 claims 5
- 239000002826 coolant Substances 0.000 claims 5
- 238000010438 heat treatment Methods 0.000 claims 2
- 230000001105 regulatory Effects 0.000 claims 2
- 230000003134 recirculating Effects 0.000 description 1
Description
プラント出力制御装置１６は、再循環流量及び制御棒位置を設定値に調整する（ステップＳ１２４）。具体的には、出力制御装置２２から再循環流量制御装置１７と制御棒制御装置１８へ、再循環流量信号、制御棒位置信号を送出し、再循環流量制御装置１７が再循環ポンプ３を制御し、制御棒制御装置１８が制御棒の４の位置を制御する。 The plant output control device 16 adjusts the recirculation flow rate and the control rod position to set values (step S124). Specifically, the output control unit 22 to the recirculation flow rate controller 17 and the control rod control system 18, the recirculation flow rate signal, sends a control rod position signal, the recirculation flow rate controller 17 controls the recirculating pump 3 Then, the control rod control device 18 controls the position of the control rod 4.
Claims (12)
前記発電機の出力目標値を生成する目標値生成装置と、前記発電機の実出力を計測するセンサと、
前記発電機の出力目標値と前記発電機の実出力との差である第１の発電機出力偏差信号に基づき前記蒸気の抽気量を設定する抽気制御装置と、
前記抽気制御装置の設定値に一致するよう前記抽気弁を駆動する抽気弁制御装置と、
前記発電機の実出力から前記抽気制御装置の抽気量の制御による前記発電機の出力への寄与分を減算した補正発電機出力と、前記発電機の出力目標値と前記補正発電機出力との差である第２の発電機出力偏差信号を出力する出力制御装置と、
前記出力制御装置からの第２の発電機出力偏差信号に応じて、前記再循環ポンプの再循環流量を調整する再循環流量制御装置と、
前記出力制御装置からの第２の発電機出力偏差信号に応じて、前記制御棒の位置を変更する制御棒制御装置とを備えた
ことを特徴とする原子力プラントの出力制御装置。 Driven by a nuclear reactor, a recirculation pump for circulating coolant in the nuclear reactor, a control rod, a regulating valve for adjusting the flow rate of steam generated in the nuclear reactor, and steam that has passed through the regulating valve A turbine, a generator driven by the turbine to generate electric power, and a bleed valve installed between the control valve and the turbine to supply a part of the steam to other equipment;
A target value generating device for generating an output target value of the generator; a sensor for measuring an actual output of the generator;
An extraction control device that sets the extraction amount of the steam based on a first generator output deviation signal that is a difference between an output target value of the generator and an actual output of the generator;
A bleed valve control device that drives the bleed valve to match a set value of the bleed control device;
The corrected generator output obtained by subtracting the contribution to the generator output by controlling the amount of extraction of the extraction control device from the actual output of the generator, the output target value of the generator, and the corrected generator output An output control device for outputting a second generator output deviation signal which is a difference;
A recirculation flow rate control device that adjusts a recirculation flow rate of the recirculation pump according to a second generator output deviation signal from the output control device;
An output control device for a nuclear power plant, comprising: a control rod control device that changes a position of the control rod in accordance with a second generator output deviation signal from the output control device.
前記抽気制御装置は、前記第１の発電機出力偏差信号として、前記第２の発電機出力偏差信号で算出された値と同一の値を使用して前記蒸気の抽気量を設定する
ことを特徴とする原子力プラントの出力制御装置。 In the nuclear power plant output control device according to claim 1,
The extraction control device sets the extraction amount of the steam using the same value as the value calculated by the second generator output deviation signal as the first generator output deviation signal. An output control device for a nuclear power plant.
前記抽気制御装置で設定した前記蒸気の抽気量は、予め定めた第１閾値より前記第１の発電機出力偏差信号が大きいときに、定格抽気量を減少させるように設定され、
前記出力制御装置で設定した前記制御棒の位置を変更する信号の値は、予め定めた第２閾値より前記第２の発電機出力偏差信号が大きいときに、前記制御棒の位置を変更するように設定され、
前記第１閾値を前記第２閾値よりも大きく設定した
ことを特徴とする原子力プラントの出力制御装置。 In the nuclear power plant output control device according to claim 1 or 2,
The steam extraction amount set by the extraction control device is set to decrease the rated extraction amount when the first generator output deviation signal is larger than a predetermined first threshold,
The value of the signal for changing the position of the control rod set by the output control device is such that the position of the control rod is changed when the second generator output deviation signal is larger than a predetermined second threshold value. Set to
The nuclear power plant output control apparatus, wherein the first threshold value is set larger than the second threshold value.
前記抽気制御装置は、前記発電機の出力目標値の変化率を演算する変化率演算器を備え、
前記発電機の出力目標値の変化率が予め定めた設定値未満の場合には、設定する抽気量を定格抽気量と同一とし、
前記発電機の出力目標値の変化率が予め定めた設定値以上のときのみ前記第１の発電機出力偏差信号に基づき抽気量を設定する
ことを特徴とする原子力プラントの出力制御装置。 In the nuclear power plant output control device according to any one of claims 1 to 3,
The extraction control device includes a change rate calculator that calculates a change rate of an output target value of the generator,
When the rate of change of the output target value of the generator is less than a preset value, the extraction amount to be set is the same as the rated extraction amount,
An output control device for a nuclear power plant, wherein the extraction amount is set based on the first generator output deviation signal only when the rate of change of the output target value of the generator is not less than a predetermined set value.
前記抽気弁を複数個備え、
前記抽気制御装置は、前記第１の発電機出力偏差信号に基づき前記蒸気の抽気量を複数の前記抽気弁のそれぞれに設定し、
設定された抽気量において、定格抽気量から変化を開始する前記第１の発電機出力偏差信号の値を抽気弁毎に異なるように設定した
ことを特徴とする原子力プラントの出力制御装置。 In the nuclear power plant output control apparatus according to any one of claims 1 to 4,
A plurality of the bleed valves;
The extraction control device sets the extraction amount of the steam to each of the plurality of extraction valves based on the first generator output deviation signal,
An output control device for a nuclear power plant, wherein the value of the first generator output deviation signal that starts changing from the rated bleed amount is set to be different for each bleed valve in the set bleed amount.
前記原子炉へ冷却材を給水する給水ポンプと、前記給水ポンプの給水流量を制御する給水制御装置と、前記原子炉への給水を抽気により加熱する給水加熱器とを備え、
前記出力制御装置は、前記抽気制御装置が設定した前記蒸気の抽気量に基づいて前記給水制御装置に水位設定値を送信し、前記給水制御装置は前記水位設定値に基づいて前記給水ポンプの給水流量を調整する
ことを特徴とする原子力プラントの出力制御装置。 In the nuclear power plant output control apparatus according to any one of claims 1 to 5,
A feed water pump for feeding coolant to the nuclear reactor, a feed water control device for controlling the feed water flow rate of the feed water pump, and a feed water heater for heating the feed water to the reactor by extraction,
The output control device transmits a water level set value to the water supply control device based on the steam extraction amount set by the extraction control device, and the water supply control device supplies water to the water supply pump based on the water level set value. An output control device for a nuclear power plant characterized by adjusting a flow rate.
前記出力制御装置は、前記発電機の出力目標値と、前記発電機の実出力とから、第１の発電機出力偏差信号を算出し、前記第１の発電機出力偏差信号に基づき、蒸気の一部を前記他の設備へ供給する前記抽気弁の抽気量を調整する第１のプロセスと、
前記発電機の実出力から前記抽気弁の抽気量の制御による前記発電機の出力への寄与分を減算した補正発電機出力を算出し、前記発電機の出力目標値と前記補正発電機出力から第２の発電機出力偏差信号を算出し、前記第２の発電機出力偏差信号に基づき前記再循環ポンプの再循環流量及び前記制御棒の位置を調整する第２のプロセスとを備え、
前記第１のプロセスと前記第２のプロセスとを並行して実施する
ことを特徴とする原子力プラントの出力制御方法。 A reactor, an adjusting valve for adjusting a flow rate of steam generated in the reactor, a turbine driven by steam passing through the adjusting valve, a generator driven by the turbine to generate electric power, and the adjusting A bleed valve installed between the valve and the turbine and capable of supplying a part of the steam to other equipment, a recirculation pump for circulating the coolant, a control rod, and an output control device An output control method for a nuclear power plant,
The output control device calculates a first generator output deviation signal from the output target value of the generator and the actual output of the generator, and based on the first generator output deviation signal, A first process for adjusting a bleed amount of the bleed valve for supplying a part to the other equipment;
A corrected generator output obtained by subtracting a contribution to the output of the generator by controlling the extraction amount of the extraction valve from the actual output of the generator is calculated, and from the output target value of the generator and the corrected generator output Calculating a second generator output deviation signal, and adjusting a recirculation flow rate of the recirculation pump and a position of the control rod based on the second generator output deviation signal,
The nuclear power plant output control method, wherein the first process and the second process are performed in parallel.
前記第１のプロセスは、前記第１の発電機出力偏差信号として、前記第２の発電機出力偏差信号で算出された値と同一の値を使用して前記蒸気の抽気量を調整する
ことを特徴とする原子力プラントの出力制御方法。 In the nuclear power plant output control method according to claim 7,
The first process uses the same value as the value calculated with the second generator output deviation signal as the first generator output deviation signal to adjust the amount of steam extracted. A nuclear power plant output control method.
前記第１のプロセスにおいて、前記蒸気の抽気量は、予め定めた第１閾値より前記第１の発電機出力偏差信号が大きいときに、定格抽気量を減少させるように設定され、
前記第２のプロセスにおいて、前記制御棒の位置を変更する信号の値は、予め定めた第２閾値より前記第２の発電機出力偏差信号が大きいときに、前記制御棒の位置を変更するように設定され、
前記第１閾値を前記第２閾値よりも大きく設定した
ことを特徴とする原子力プラントの出力制御方法。 In the nuclear power plant output control method according to claim 7 or 8,
In the first process, the steam extraction amount is set so as to decrease the rated extraction amount when the first generator output deviation signal is larger than a predetermined first threshold value.
In the second process, the value of the signal for changing the position of the control rod is such that the position of the control rod is changed when the second generator output deviation signal is larger than a predetermined second threshold value. Set to
The nuclear power plant output control method, wherein the first threshold value is set larger than the second threshold value.
前記出力制御装置は、前記発電機の出力目標値の変化率を演算する変化率演算器を備え、
前記第１のプロセスにおいて、前記発電機の出力目標値の変化率が予め定めた設定値未満の場合には、設定する抽気量を定格抽気量と同一とし、
前記発電機の出力目標値の変化率が予め定めた設定値以上のときのみ前記第１の発電機出力偏差信号に基づき抽気量を調整する
ことを特徴とする原子力プラントの出力制御方法。 In the nuclear power plant output control method according to any one of claims 7 to 9,
The output control device includes a change rate calculator that calculates a change rate of an output target value of the generator,
In the first process, when the rate of change of the output target value of the generator is less than a predetermined set value, the extraction amount to be set is the same as the rated extraction amount,
An output control method for a nuclear power plant, characterized in that the extraction amount is adjusted based on the first generator output deviation signal only when the rate of change of the output target value of the generator is equal to or greater than a predetermined set value.
前記抽気弁は複数個を備え、
前記第１のプロセスは、前記発電機の出力目標値と、前記発電機の実出力とから、第１の発電機出力偏差信号を算出し、前記第１の発電機出力偏差信号に基づき、蒸気の一部を他の設備へ供給する複数の前記抽気弁の抽気量を調整し、
設定された抽気量において、定格抽気量から変化を開始する前記第１の発電機出力偏差信号の値を抽気弁毎に異なるように設定した
ことを特徴とする原子力プラントの出力制御方法。 In the nuclear power plant output control method according to any one of claims 7 to 10,
The bleed valve has a plurality,
The first process calculates a first generator output deviation signal from the output target value of the generator and the actual output of the generator, and based on the first generator output deviation signal, Adjusting the extraction amount of the plurality of extraction valves for supplying a part of the
An output control method for a nuclear power plant characterized in that, in the set extraction amount, the value of the first generator output deviation signal that starts changing from the rated extraction amount is set to be different for each extraction valve.
前記出力制御装置は、前記発電機の出力目標値と、前記発電機の実出力とから、第１の発電機出力偏差信号を算出し、前記第１の発電機出力偏差信号に基づき、蒸気の一部を前記他の設備へ供給する前記抽気弁の抽気量を調整する第１のプロセスと、
前記発電機の実出力から前記抽気弁の抽気量の制御による前記発電機の出力への寄与分を減算した補正発電機出力を算出し、前記発電機の出力目標値と前記補正発電機出力から第２の発電機出力偏差信号を算出し、前記第２の発電機出力偏差信号に基づき前記再循環ポンプの再循環流量及び前記制御棒の位置を調整する第２のプロセスと、
前記給水加熱器への抽気量に基づき、前記原子炉への給水流量を調整する第３のプロセスとを備え、
前記第１のプロセスと前記第２のプロセスと前記第３のプロセスとを並行して実施する
ことを特徴とする原子力プラントの出力制御方法。 A reactor, an adjusting valve for adjusting a flow rate of steam generated in the reactor, a turbine driven by steam passing through the adjusting valve, a generator driven by the turbine to generate electric power, and the adjusting A bleed valve installed between a valve and the turbine to supply a part of the steam to other equipment, a recirculation pump for circulating the coolant, a control rod, and a coolant to the reactor A nuclear power plant output control method comprising: a feed water pump for feeding water; a feed water control device for controlling a feed water flow rate of the feed water pump; a feed water heater for heating feed water to the nuclear reactor by extraction; and an output control device There,
The output control device calculates a first generator output deviation signal from the output target value of the generator and the actual output of the generator, and based on the first generator output deviation signal, A first process for adjusting a bleed amount of the bleed valve for supplying a part to the other equipment;
A corrected generator output obtained by subtracting a contribution to the output of the generator by controlling the extraction amount of the extraction valve from the actual output of the generator is calculated, and from the output target value of the generator and the corrected generator output A second process of calculating a second generator output deviation signal and adjusting a recirculation flow rate of the recirculation pump and a position of the control rod based on the second generator output deviation signal;
A third process for adjusting the feed water flow rate to the reactor based on the amount of bleed air to the feed water heater;
The nuclear power plant output control method, wherein the first process, the second process, and the third process are performed in parallel.
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| Application Number | Priority Date | Filing Date | Title |
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| JP2016083756A JP6608324B2 (en) | 2016-04-19 | 2016-04-19 | Power plant output control apparatus and method |
Applications Claiming Priority (1)
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| JP2016083756A JP6608324B2 (en) | 2016-04-19 | 2016-04-19 | Power plant output control apparatus and method |
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| JP2017194312A JP2017194312A (en) | 2017-10-26 |
| JP2017194312A5 true JP2017194312A5 (en) | 2019-02-14 |
| JP6608324B2 JP6608324B2 (en) | 2019-11-20 |
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| JP6865186B2 (en) * | 2018-02-28 | 2021-04-28 | 日立Ｇｅニュークリア・エナジー株式会社 | Load tracking device and nuclear power plant with it |
| CN110155296A (en) * | 2019-04-03 | 2019-08-23 | 中国船舶重工集团公司第七一九研究所 | Ocean nuclear power platform auxiliary steam converting system |
| US11402131B1 (en) * | 2021-01-18 | 2022-08-02 | Renewable Energy Aggregators Inc. | Hardened solar energy collector system |
| JP7489340B2 (en) | 2021-01-25 | 2024-05-23 | 日立Ｇｅニュークリア・エナジー株式会社 | Nuclear power plant output control device and output control method |
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| US4707324A (en) * | 1984-12-27 | 1987-11-17 | Westinghouse Electric Corp. | Controlling the response of a pressurized water reactor to rapid fluctuations in load |
| JP2559377B2 (en) * | 1986-10-03 | 1996-12-04 | 株式会社日立製作所 | Controller for steam generation plant |
| JPS63204003A (en) * | 1987-02-20 | 1988-08-23 | 株式会社日立製作所 | Steam generation plant output controller |
| JPH01248098A (en) * | 1988-03-30 | 1989-10-03 | Hitachi Ltd | Operating device for small and short ranged load following of boiling water nuclear reactor |
| JPH04278499A (en) * | 1991-03-07 | 1992-10-05 | Hitachi Ltd | Output controlling device of nuclear power plant |
| JP2902217B2 (en) * | 1992-07-13 | 1999-06-07 | 株式会社日立製作所 | Output control method and apparatus for nuclear power plant |
| JPH09304586A (en) * | 1996-05-20 | 1997-11-28 | Toshiba Corp | Boiling water nuclear power plant |
| JP3362603B2 (en) * | 1996-07-15 | 2003-01-07 | 株式会社日立製作所 | Reactor power control device |
| JP2000111003A (en) * | 1998-10-06 | 2000-04-18 | Ishikawajima Harima Heavy Ind Co Ltd | Control method of extraction fluctuation boiler |
| JP2008128881A (en) * | 2006-11-22 | 2008-06-05 | Hitachi-Ge Nuclear Energy Ltd | Operation method of nuclear power plant |
| US20080317191A1 (en) * | 2007-06-20 | 2008-12-25 | Masao Chaki | Operating method of nuclear reactor and nuclear power generation plant |
| KR20150083374A (en) * | 2014-01-09 | 2015-07-17 | 두산중공업 주식회사 | Apparatus and method for reactor power control of steam turbine power generation system |
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