GB2535834A - Method for segmental control of auxillary feedwater flow - Google Patents

Method for segmental control of auxillary feedwater flow Download PDF

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Publication number
GB2535834A
GB2535834A GB1522104.7A GB201522104A GB2535834A GB 2535834 A GB2535834 A GB 2535834A GB 201522104 A GB201522104 A GB 201522104A GB 2535834 A GB2535834 A GB 2535834A
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GB
United Kingdom
Prior art keywords
control
auxiliary feedwater
valve
control valve
feedwater flow
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Application number
GB1522104.7A
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GB2535834B (en
GB201522104D0 (en
Inventor
Shang Xuelian
Guo Lin
Zhang Ruiping
Yan Guiyin
Zhang Dong
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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Publication of GB201522104D0 publication Critical patent/GB201522104D0/en
Publication of GB2535834A publication Critical patent/GB2535834A/en
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Publication of GB2535834B publication Critical patent/GB2535834B/en
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/086—Pressurised water reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F01—MACHINES OR ENGINES IN GENERAL; ENGINE PLANTS IN GENERAL; STEAM ENGINES
    • F01K—STEAM ENGINE PLANTS; STEAM ACCUMULATORS; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES
    • F01K5/00—Plants characterised by use of means for storing steam in an alkali to increase steam pressure, e.g. of Honigmann or Koenemann type
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22D—PREHEATING, OR ACCUMULATING PREHEATED, FEED-WATER FOR STEAM GENERATION; FEED-WATER SUPPLY FOR STEAM GENERATION; CONTROLLING WATER LEVEL FOR STEAM GENERATION; AUXILIARY DEVICES FOR PROMOTING WATER CIRCULATION WITHIN STEAM BOILERS
    • F22D5/00—Controlling water feed or water level; Automatic water feeding or water-level regulators
    • F22D5/26—Automatic feed-control systems
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • 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
    • 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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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Emergency Management (AREA)
  • Business, Economics & Management (AREA)
  • Mechanical Engineering (AREA)
  • Thermal Sciences (AREA)
  • Chemical & Material Sciences (AREA)
  • Combustion & Propulsion (AREA)
  • Safety Devices In Control Systems (AREA)
  • Control Of Turbines (AREA)

Abstract

A method of control of the auxiliary water in nuclear power plants is characterized in that a solenoid valve of an auxiliary feedwater flow control valve is energized via an automatic interlock signal after an auxiliary feedwater system is put into operation. A control system detects the water level in a steam generator and performs segmental control of opening of the auxiliary feedwater control valve in response to a preset value so as to maintain the water level in the steam generator. After the control valve is removed out of the control mode, the solenoid valve of the auxiliary feedwater flow control valve is de-energized and the control valve is restored to fully-open position. The control of the valve based on detecting of the water level can have four detectors with the water level change being based on a two out of four voting logic to overcome any signal faults, thus allowing for a redundancy configuration. The system may also be designed with a manual adjustment in addition to the automatic control.

Description

METHOD FOR SEGMENTAL CONTROL OF AUXILIARY
FEEDWATER FLOW
Field of the invention
The present invention relates to automatic control technology of nuclear power plants, and more particularly, to a control method for segmental control of auxiliary feedwater flow to match the water level in steam generators (SGs).
Description of Related Art
The auxiliary feedwater system is an important Engineered Safety Feature Actuation System in the Advanced Pressurized Water Reactor Power Plants. In the event that an accident occurs, it provides make-up water to the Steam Generator in order to remove residual heat from the reactor. This system is equipped with six auxiliary feedwater flow control valves, three in Train A and Train B respectively.
In the conventional nuclear power plant design, the auxiliary feedwater system has the following characteristics: The failure position of an auxiliary feedwater flow control valve is at its full-open position. Each auxiliary feedwater flow control valve is equipped with two solenoid valves connected in series which are powered and controlled respectively by Train A and Train B. The loss of either solenoid valve's train power supply would result in the auxiliary feedwater flow control valve being fully opened and the valve only operates in control mode when the solenoid valves of both Train A and Train B are energized simultaneously. After the auxiliary feedwater system is started up, the operator must based on his observation and judgment on the operating parameters of the power plant, set the valve to the manual control mode and manually adjust the opening of the auxiliary feedwater flow control valve so as to control the auxiliary feedwater flow. This design would lead to larger effort intensity of operators and increase the probability of accidents caused by human factor. Moreover, loss of control signal from either Train A or Train B or power supply to any of the solenoid valves would result in the six control valves being fully opened and the operators cannot control the opening of the valves from the main control room. Consequently, the auxiliary feedwater system supplies make-up water to the steam generator at the maximum flow rate and, as a result, excessive amount of auxiliary feedwater would result in overflow of the steam generator.
In the design of ACP 1000 nuclear power plants, for the sake of increased safety considerations, there is a requirement that no manual intervention is allowed within a certain period of time following an accident.
To meet the above requirement, increase the safety of auxiliary feedwater system and reduce post-accident manual intervention, there is a need to take measures to address the problem correspondingly. Specifically, by adjusting the opening of the auxiliary feedwater flow control valves automatically, the water level in the steam generator is maintained within the range to meet the functional requirements without any overflow.
Summary of the Invention
The objective of the present invention is to provide a segmental control method for the control of auxiliary feedwater flow according to the water level in steam generators thus meeting the safety requirements of nuclear power plants.
To achieve the objective described above, the present invention employs the technical solutions below: A control method for segmental control of auxiliary feedwater flow, comprising: energizing a solenoid valve of an auxiliary feedwater flow control valve via automatic interlock signal after an auxiliary feedwater system is put into operation such that the control valve is placed into control mode automatically; a control system judges water level of a steam generator and segmentally adjusts the opening of the auxiliary feedwater control valve in response to a preset value of the high or low water level so as to maintain the water level in the steam generator within a certain range; when the control valve is withdrawed from control mode, the solenoid valve of the auxiliary feedwater flow control valve comes to be de-energized and the control valve is restored to fully-opening position.
Further, the said control method for segmental control of auxiliary feedwater flow, wherein each of the auxiliary feedwater flow control valves is equipped with only one solenoid valve which is powered and controlled by the train same with the auxiliary feedwater flow control valve; a control logic of the auxiliary feedwater flow control valve matches with auxiliary feedwater pipeline to allow for redundancy design, the redundancy design is realized by separating the six auxiliary feedwater flow control valves and corresponding pipes and pumps into two independent control loops, which belongs to Train A and Train B respectively, so that loss of power supply or control signal from any train will not impact the normal operation of the other train.
Further, the said control method for segmental control of auxiliary feedwater flow, wherein the water level measuring signals of the steam generator are in redundant configuration which meets the single failure criteria; the signals are collected respectively by four protection groups and compared with the preset threshold of high and low water levels of the steam generator respectively, and then the comparison results are judged through two-out-of-four voting logic to get the opening of the valve, and the high redundancy levels ensures the high reliability and meets with single failure criteria; the control logic for the segmental control is processed in processors in redundancy configuration, which can further ensure redundancy and validity of the signal and meet the requirements of safety functions.
Further, the said control method for segmental control of auxiliary feedwater flow, wherein the control system is designed with manual adjustment function in addition to the automatic segmental control to ensure that manual intervention is possible when necessary.
Further, the said control method for segmental control of auxiliary feedwater flow, wherein after the auxiliary feedwater flow control valve is placed into the segmental control mode, the control system performs the control as follows: When the water level in the steam generator reaches a high preset value, the opening of the control valve is in the range of 5-40%; When the water level in the steam generator reaches a low preset value, the opening of the control valve is in the range of 80-100%; When the water level in the steam generator is between the high preset value and the low preset valve, the controller maintains the output at the preceding time and the opening of the control valve remains unchanged; After get into the segmental control mode, the auxiliary feedwater control valve will be kept under the mode until a reset signal appears and then the control valve will quit the control mode and be restored to the fully-opening position.
The advantageous effects of the present invention are as follows: Each auxiliary feedwater control valve is equipped with one solenoid valve which is controlled or powered by a single train, solving the problem that a single failure occurring in any train results in the fully open of whole valves. The automatic segmental control design enables the water level in the steam generator to be maintained within the range so that a sufficient but not excessive auxiliary feedwater flow is available to remove residual heat from the cores without manual intervention in a period of time. The method of the present invention avoids the potential risk in human operation and improves the safety and stability of the power plants on a certain extent by reducing manual intervention.
Brief Description of the Drawings
Fig.1 is a schematic diagram showing the auxiliary feedwater flow segmental control method in accordance with the present invention.
Description of the preferred embodiment
One or more advantageous features as described herein will be readily apparent from the following detailed description of one or more embodiments when taken in connection with the accompanying drawings.
After the auxiliary feedwater system is put into operation, in order to prevent overflow of the steam generator within a certain period of time and ensure sufficient feedwater flow, the control valves will be put into segmental control mode in response to the water level in the steam generator.
Each auxiliary feedwater flow control valve is equipped with one solenoid pilot valve which is part of the former and is installed on an air line of the auxiliary feedwater flow control valve. As the control signal and power supply of each auxiliary feedwater flow control valve is sourced from a single train, each train's failure has no effect on the valves in the other train.
The water level measuring signal of the steam generator is in redundant configuration so as to meet the requirement for single fault. The signals are collected respectively by four protection groups and compared with the preset values of high and low water levels of the steam generator for threshold value and then the opening of the valve is judged after two-out-of-four voting logic.
Embodiments: As shown in Fig.1, the auxiliary feedwater to each steam generator is collected through a manifold which receives auxiliary feedwater flow respectively from Train A and Train B. For simplicity, Fig.1 depicts only the segmental control of auxiliary feedwater flow control valve for Train A and the control strategy for Train B is identical.
The controller of the system receives four signals: water level high and low signal of steam generator; manual/automatic transfer switch (for switch between manual and automatic modes); manual/automatic control station signal (outputting the opening command when the manual mode is selected).
After the auxiliary feedwater system is put into operation, the RS trigger receives the starting command and the solenoid valve of the flow control valve is energized, the valve is placed into the segmental control mode and the controller outputs the signal of opening command in response to the comparison between the water level in the steam generator and the threshold value. The signals of steam generator water level are collected by the protection groups IP-IVP and compared with the preset values of high and low water level (by XU). When the water level reaches the high value, the output of high threshold comparison is 1. The comparison results of multiple measuring channels are judged through two-out-of-four voting logic, and the voting results are sent to the controller which gives the control signal to the electrical/pneumatic converter (EP) according to the results. For example, if the voting result shows that the level is high, the controller will output a valve opening command in the range of 5%-40%. In this embodiment, the opening of the valve is adjusted to 10%. Which will reduce the valve's opening, the feedwater flow is reduced as well and, consequently, the water level in the steam generator is lowered. When the water level reaches the low preset value, the output of low threshold comparison is 1. After the two-out-of-four voting logic of multiple channels, the voting results are sent to the controller. If the voting result shows that the level is low, the controller will output a valve opening in the range of 80%-100%. In this embodiment, the opening of the valve is adjusted to 100%. When the water level in the steam generator is between the high and low threshold, the controller maintains the output at the preceding time and the opening of the control valve remains unchanged. In this way, the water level in the steam generator is controlled within the range to meet the functional requirements. Until a reset signal is generated and the RS trigger receives the reset command, the control valve quits the control mode and is restored to the fully-opening position.
An RS trigger is shown in the figure. The starting command of the auxiliary feedwater pumps is taken as the input of the set of the RS trigger and the signal from the S output terminal is sent to the solenoid valve, ensuring that after the auxiliary feedwater system is started up, the solenoid valve can be energized and the valve is adjustable.
Manual/automatic undisturbed switching functionality is provided in this solution. To allow manual intervention when necessary, the controller can receive manual control signal, in addition to its automatic control functionality. When transfer from the automatic mode to the manual mode occurs, the manual signal adjusts the valve from the current opening without any perturbation. The manual transfer signal is combined with the output signal of the RS trigger with a logic "OR" and the result is sent to the solenoid valve to ensure that the valve in the manual mode is energized and adjustable.
The logic relations can be implemented through logic configuration in the digital control system DCS or, alternatively, can be realized through the dedicated program module in the DCS.
Focusing on the design of the control system, the present invention deals with a specific design solution for controlling auxiliary feedwater flow after the auxiliary feedwater system is put into operation. It takes into account the two stages where the auxiliary feedwater system is put into use and removed out of use and can be used for any operating conditions of nuclear power plants. The automatic segmental control described herein ensures not only the functionality of automatic flow adjustment of the auxiliary feedwater system but also the functionality of adjusting the auxiliary feedwater flow without manual intervention following an accident. In addition, the built-in manual adjustment functionality provides a means for manual intervention when necessary.
The above disclosure is related to the detailed technical contents and inventive features thereof. People skilled in this field may proceed with a variety of modifications and replacements based on the disclosures and suggestions of the invention as described without departing from the characteristics thereof. Nevertheless, although such modifications and replacements are not fully disclosed in the above descriptions, they have substantially been covered in the following claims as appended.

Claims (5)

  1. Claims 1. A control method for segmental control of auxiliary feedwater flow, characterized in that: energizing a solenoid valve of an auxiliary feedwater flow control valve via automatic interlock signal after an auxiliary feedwater system is put into operation such that the control valve is placed into control mode automatically; a control system judges high or low water level in a steam generator and performs segmental control to the opening of the auxiliary feedwater control valve in response to a preset value of the high or low water level so as to maintain the water level in the steam generator within a certain range; after the control valve is removed out of the control mode, the solenoid valve of the auxiliary feedwater flow control valve is de-energized and the control valve is restored to fully-opening position.
  2. 2. The control method for segmental control of auxiliary feedwater flow as claimed in claim 1, wherein each of the auxiliary feedwater flow control valves is equipped with one solenoid valve which is powered and controlled by the train to which the auxiliary feedwater flow control valve belongs; a control logic of the auxiliary feedwater flow control valve matches with auxiliary feedwater pipeline to allow for redundancy design such that loss of power supply or control signal from any train will not impact normal operation of the other trains.
  3. 3. The control method for segmental control of auxiliary feedwater flow as claimed in claim 1, wherein water level measuring signal of the steam generator is in redundant configuration so as to meet the requirement for single fault; the signal is collected respectively by four protection groups and is compared with the preset values of high or low water levels of the steam generator for a threshold value and then the opening of the valve is judged through a two-out-of-four voting logic; the control logic for the segmental control is processed in processors in redundancy configuration, which can further ensure redundancy and validity of the signal and meet the requirements of safety functions.
  4. 4. The control method for segmental control of auxiliary feedwater flow as claimed in claim 3, wherein the control system is designed with a manual adjustment function in addition to the automatic segmental control to ensure that manual intervention is possible when necessary.
  5. 5. The control method for segmental control of auxiliary feedwater flow as claimed in any one of claims 1 to 4, wherein after the auxiliary feedwater flow control valve is placed into the segmental control mode, when the water level in the steam generator reaches the preset values of high and low water levels, the control system performs segmental control to the auxiliary feedwater flow control valve as follows: When the water level in the steam generator reaches the high preset value, the opening of the control valve is in the range of 5-40%; When the water level in the steam generator reaches the low preset value, the opening of the control valve is in the range of 80-100%; When the water level in the steam generator is between the high preset value and the low preset valve, the controller maintains an output at a preceding time and the opening of the control valve remains unchanged; After get into the segmental control mode, the auxiliary feedwater control valve will be kept under the control mode until a reset signal appears and then the control valve will quit the control mode and be restored to the fully-opening position.
GB1522104.7A 2015-01-08 2015-12-15 Method for segmental control of auxillary feedwater flow Active GB2535834B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201510009327.XA CN104681111A (en) 2015-01-08 2015-01-08 Auxiliary water supply flow segmented regulation control method

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GB201522104D0 GB201522104D0 (en) 2016-01-27
GB2535834A true GB2535834A (en) 2016-08-31
GB2535834B GB2535834B (en) 2019-04-10

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Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN107895599A (en) * 2017-10-12 2018-04-10 中广核研究院有限公司 A kind of voltage-stablizer water level measurement method and voltage-stablizer
CN109581923B (en) * 2018-12-05 2021-10-15 深圳中广核工程设计有限公司 Water supply control system for nuclear power station
CN111486438B (en) * 2020-03-18 2023-05-12 中国核电工程有限公司 Control method for preventing overflow of steam generator caused by auxiliary water supply system

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JPS5780182A (en) * 1980-11-07 1982-05-19 Hitachi Ltd Minimum-flow control system for condensate system
JPH11271491A (en) * 1998-03-24 1999-10-08 Toshiba Corp Reactor feed water controller
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US20060029179A1 (en) * 2002-09-25 2006-02-09 Srinivasan Jagannathan S Method for calibrating steam generator water level measurement
EP2587142A2 (en) * 2011-10-26 2013-05-01 Mitsubishi Heavy Industries Auxiliary feedwater valve control apparatus of steam generator
CN104696943A (en) * 2013-12-09 2015-06-10 徐州传庆电子科技有限公司 Safe and automatic heating and water feeding device for boiler

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5780182A (en) * 1980-11-07 1982-05-19 Hitachi Ltd Minimum-flow control system for condensate system
JPH11271491A (en) * 1998-03-24 1999-10-08 Toshiba Corp Reactor feed water controller
US20060029179A1 (en) * 2002-09-25 2006-02-09 Srinivasan Jagannathan S Method for calibrating steam generator water level measurement
US20050072380A1 (en) * 2003-07-19 2005-04-07 Korea Power Engineering Company, Inc. Feedwater control system considering pressure drop of feedwater control valve in nuclear power plant and control method therefor
EP2587142A2 (en) * 2011-10-26 2013-05-01 Mitsubishi Heavy Industries Auxiliary feedwater valve control apparatus of steam generator
CN104696943A (en) * 2013-12-09 2015-06-10 徐州传庆电子科技有限公司 Safe and automatic heating and water feeding device for boiler

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Publication number Publication date
GB2535834B (en) 2019-04-10
GB201522104D0 (en) 2016-01-27
CN104681111A (en) 2015-06-03

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