CN109116722A - Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation - Google Patents

Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation Download PDF

Info

Publication number
CN109116722A
CN109116722A CN201710487736.XA CN201710487736A CN109116722A CN 109116722 A CN109116722 A CN 109116722A CN 201710487736 A CN201710487736 A CN 201710487736A CN 109116722 A CN109116722 A CN 109116722A
Authority
CN
China
Prior art keywords
module
main
power station
intermodule
nuclear power
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201710487736.XA
Other languages
Chinese (zh)
Inventor
董哲
宋茂轩
潘奕斐
黄晓津
张作义
吴宗鑫
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Tsinghua University
Original Assignee
Tsinghua University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Tsinghua University filed Critical Tsinghua University
Priority to CN201710487736.XA priority Critical patent/CN109116722A/en
Publication of CN109116722A publication Critical patent/CN109116722A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G05CONTROLLING; REGULATING
    • G05BCONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
    • G05B11/00Automatic controllers
    • G05B11/01Automatic controllers electric
    • G05B11/36Automatic controllers electric with provision for obtaining particular characteristics, e.g. proportional, integral, differential
    • G05B11/42Automatic controllers electric with provision for obtaining particular characteristics, e.g. proportional, integral, differential for obtaining a characteristic which is both proportional and time-dependent, e.g. P. I., P. I. D.

Landscapes

  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Automation & Control Theory (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Intermodule Coordinated Control Scheme the invention discloses multi-module type nuclear power station with base load operation, belongs to Nuclear Energy Science and Engineering field.For the multi-module type nuclear power station formed containing n nuclear steam supply system module, to make power station band base load operation, its intermodule Coordinated Control Scheme includes n module feedwater flow feedback control loop, 1 main steam pressure feedback control loop and 1 main feedwater flow feedback control loop.Solves the Harmonic Control that multiple nuclear steam supply system modules are generated because sharing water supply main pipe and steam main pipe.

Description

Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation
Technical field
The invention belongs to Nuclear Energy Science and Engineering fields, are a kind of multi-module type nuclear power station band base loads specifically The intermodule Coordinated Control Scheme of operation.
Background technique
The Soviet Union in 1954 builds up First prototype reactor of nuclear power plant Ao Buningsike nuclear power plant in the world.Then, nuclear power station Development can be summarized as two main lines.First is that the single module formula nuclear energy unit that development is large-scale.Nuclear steam supply system in nuclear power station (Nuclear Steam Supply System, NSSS) module number remains single module, by improve single heap output power come Increase power station unit capacity, mainly there is the AP1000 in the U.S., European EPR, the CAP1400/1700 in China and China dragon No. 1. Second is that developing multi-module type nuclear energy unit.To guarantee safety, the output thermal power of reactor is restricted, and single heap exports hot merit Rate is in 300MWthHereinafter, i.e. small modules formula reactor (Small Modular Reactor, SMR).It is multiple have it is inherently safe Property SMR multi-module type nuclear energy unit is constructed by " more one machines of heap band " technology, multiple NSSS modules and vapour drive same set of vapour Turbine generator group mainly has mPower, the Nuscale in the U.S., the HTR-PM and HTR-PM600 in China.Compared to large-scale list Modular nuclear energy unit has taken into account safety while multi-module type nuclear energy unit is realized through property.
Coordinated control (referred to as " multimode coordinated control ") technology of multi-module type nuclear power station is to realize " more one machines of heap band " Key technology.Multimode coordinated control includes the coordinated control of NSSS inside modules and NSSS intermodule coordinated control.
NSSS inside modules coordinated control is current research hotspot, for the function of realizing different Engineering Controls requirements, state Inside and outside many scholars study and have developed corresponding control strategy.NSSS inside modules coordinated control includes reactor control System, steam generator control, reactor and steam generator coordinated control.Power control is the key that reactor control control. For the local stability for realizing power control, classic control such as PID control, linear optimal contro8 are developed;In order to enhance power control The anti-interference ability of system processed realizes constrained performance optimization, has developed robust control, Model Predictive Control;In order to realize The wide range load tracking of power control has developed nonlinear Control, intelligent control.Steam generator is controlled, engineering Control requires related with the characteristic of steam generator.For U-tube steam generator (UTSG), there are biggish water for secondary side Hold, need to carry out water level control, to alleviate false water level phenomenon, enhances the stability of control, optimal control performance has developed line Property optimum control, Model Predictive Control, robust control and intelligent control.For continuous steam generator, secondary side water Appearance is smaller, but the sensibility that outlet steam temperature disturbs first and second side is stronger, to stablize its outlet steam temperature, development Classic control, nonlinear Control, intelligent control.For reactor and steam generator coordinated control, due to the core of active service operation Power station is mostly pressurized-water reactor nuclear power plant, and the coupling between reactor and UTSG is weaker, is studied in the world less.Domestic Tsinghua University is directed to The power station modular high temperature gas cooled reactor (MHTGR), proposes model-free adaption coordinated control.
For NSSS intermodule coordinated control, study at present fewer.A kind of patent " multi-module type high temperature gas cooled reactor nuclear power Water-supply scheme, dynamic model and the regulation method stood " give a kind of multi-module type HTGR Nuclear Power Plant band base load The intermodule control method for coordinating of operation, but its power station uses independent water scheme, and each NSSS module is equipped with independent water pump Carry out water supply.For the multi-module type nuclear power station using water supply piping-main scheme that this patent is related to, multiple NSSS modules share a set of Feed pump, each module assignment have feed-regulating valve to carry out assignment of traffic, and above-mentioned control method for coordinating is simultaneously not suitable for, thus need Develop new intermodule control method for coordinating.
Summary of the invention
The purpose of the present invention is be intended to provide intermodule coordinated control side of the multi-module type nuclear power station with base load operation Case solves the Harmonic Control that multiple NSSS modules are generated because sharing water supply main pipe and steam main pipe.
To realize the above-mentioned technical purpose, The technical solution adopted by the invention is as follows:
Intermodule Coordinated Control Scheme the present invention provides multi-module type nuclear power station with base load operation;
For the multi-module type nuclear power station containing n nuclear steam supply system (NSSS) module composition, to make power station tape base This load operation, intermodule Coordinated Control Scheme include n module feedwater flow feedback control loop, 1 main steam pressure Feedback control loop and 1 main feedwater flow feedback control loop.
It further limits, wherein the steam generator in NSSS module is once through steam generator (Once-Through Steam Generator, OTSG), and OTSG secondary side outlet vapor is superheated steam.
It further limits, includes module feedwater flow control system, mould in the module feedwater flow feedback control loop Block feedwater flow control system generates the setting value of feed-regulating valve aperture according to module feed-water quality flow deviation, passes through adjusting The aperture of feed-regulating valve realizes the control of module feedwater flow.
Preferably, module feed-water quality flow deviation is by module feed-water quality flow measurements and module feed-water quality flow Setting value determines, and module feed-water quality flow setting value by reactor capability dispensing controller according to network load setting value and Generation load measured value generates.
It further limits, includes main steam pressure control system, main steam in the main steam pressure feedback control loop Control pressurer system generates the setting value of main steam control valve aperture according to main steam pressure deviation, by adjusting main steam control valve Aperture realizes the control of main steam pressure.
Preferably, main steam pressure deviation is determined by main steam pressure measured value and main steam pressure setting value, and main steaming Steam pressure setting value is generated by reactor capability dispensing controller according to network load setting value and generation load measured value.
It further limits, the main feedwater flow feedback control loop includes main feedwater flow control system, main to water flow Amount control system generates the setting value of speed of feedwater according to main feed-water quality flow deviation, is realized by adjusting speed of feedwater Main feedwater flow control.
Preferably, main feed-water quality flow deviation is by main feed-water quality flow setting value and main feed-water quality flow measurements Determine, and main feed-water quality flow setting value by reactor capability dispensing controller according to network load setting value and generation load Measured value generates.
The present invention has following advantages:
Realize the coordinated control of multiple NSSS intermodules.Multiple NSSS modules are based on water supply/steam main pipe parallel connection building Large-scale multi-module type nuclear power station, the variation of any one NSSS module feedwater flow all can cause to disturb to main steam pressure, and lead Steam pressure variation can cause to disturb to other NSSS module feedwater flows again, be unfavorable for the stable operation in power station.Control program Comprising module feedwater flow controller, main steam pressure control device and main feedwater flow controller, any one module is to water flow Amount variation will make control actuator all in system participate in control, to realize the stabilization of system.
Detailed description of the invention
The present invention can be further illustrated by the nonlimiting examples that attached drawing provides;
Attached drawing 1 is the closed loop configuration of intermodule Coordinated Control Scheme;
Attached drawing 2 is two modular nuclear power station structure schematic diagrams;
Attached drawing 3 is 1#NSSS module feedwater flow feedback control loop;
Attached drawing 4 is 2#NSSS module feedwater flow feedback control loop;
Attached drawing 5 is main steam pressure feedback control loop;
Attached drawing 6 is main feedwater flow feedback control loop;
Attached drawing 7 is response curve.
Specific embodiment
In order to make those skilled in the art that the present invention may be better understood, with reference to the accompanying drawings and examples to this hair Bright technical solution further illustrates.
Intermodule Coordinated Control Scheme the invention discloses multi-module type nuclear power station with base load operation, it is specific real It is as follows to apply process:
By taking a two modular nuclear power stations as an example, being discussed in detail for conceptual design, the structural schematic diagram in power station such as Fig. 2 are carried out It is shown.(1) intermodule Coordinated Control Scheme
For make power station band base load operation, Coordinated Control Scheme include 2 module feedwater flow feedback control loops, 1 main steam pressure feedback control loop and 1 main feedwater flow feedback control loop, control loop such as Fig. 3,4,5 and 6 institute Show.Each control system is output and input as shown in table 1.
Table 1
(2) process variable measures
Process variable involved in control system: 1~2#NSSS module feedwater flow measured value, main steam pressure measurement Value, the measurement scheme of main feedwater flow measured value are as shown in table 2.
Table 2
(3) controller design and parameter tuning
1#NSSS module feedwater flow controller, 2#NSSS mould are designed using pid control algorithm easy to implement in engineering Block feedwater flow controller, main steam pressure control device, main feedwater flow controller, the adjusting of controller parameter are shown in Table 3.
Table 3
(4) control performance is verified
Numerical simulation operating condition:
A) initial: it is 100% power station full power (Plant Full Power, PFP), main feedwater flow that power station, which runs power, For 192kg/s, main steam pressure 13.24MP.It is 100% full reactor power that 1#~2#NSSS module, which runs power, (Reactor Full Power, RFP), module feedwater flow are 96kg/s.
B) the positive setting power level step by 100%RFP to 90%RFP is applied to 1#NSSS, corresponding module is given Water flow is respectively 96kg/s, 86.4kg/s, and main feedwater flow is respectively 192kg/s, 182.4kg/s.2#NSSS module water supply Flow remains 96kg/s, and main steam pressure remains 13.24MPa.
The response curve for making 1~2#NSSS module feed-water quality flow, main steam pressure, main feedwater flow respectively, is shown in Fig. 7.
As seen in Figure 7, apply the positive setting power level rank by 100%RFP to 90%RFP to 1#NSSS Jump causes module feedwater flow deviation to increase, since 1#NSSS module is given so that 1#NSSS module feedwater flow setting value reduces The feedback effect of water controller, 1#NSSS module feedwater flow are down to 86.4kg/s by 96kg/s step.Similarly, since main water supply The feedback effect of flow controller, main feedwater flow are down to 182.4kg/s by 192kg/s step.And 1#NSSS module is to water flow Amount, which reduces, will cause main steam pressure reduction, and main steam pressure reduces will cause the increase of 2#NSSS module feedwater flow again, due to The feedback effect of main steam pressure control device, 2#NSSS module feedwater flow controller, main steam pressure remain 13.24MPa, 2#NSSS module feedwater flow remains 96kg/s.1#NSSS module sets feedwater flow and changes so that all actuators in system Coordinate to participate in control, realizes the stabilization of system.
The above process is the complete reality of intermodule Coordinated Control Scheme of the multi-mode nuclear power station with base load operation Apply process.Multi-mode nuclear power station provided by the invention is carried out with the intermodule Coordinated Control Scheme of base load operation above It is discussed in detail.The explanation of specific embodiment is merely used to help understand method and its core concept of the invention.It should be pointed out that pair For those skilled in the art, without departing from the principle of the present invention, the present invention can also be carried out Some improvements and modifications, these improvements and modifications also fall within the scope of protection of the claims of the present invention.

Claims (8)

1. intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation, it is characterised in that: for containing n The multi-module type nuclear power station of nuclear steam supply system module composition, to make power station band base load operation, intermodule coordinates control Scheme processed includes n module feedwater flow feedback control loop, and 1 main steam pressure feedback control loop and 1 master are to water flow Measure feedback control loop.
2. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 1 with base load operation, Be characterized in that: the steam generator in the NSSS module is once through steam generator, and once through steam generator secondary side goes out Mouth steam is superheated steam.
3. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 1 or 2 with base load operation, It is characterized by: including module feedwater flow control system in the module feedwater flow feedback control loop, module is to water flow Amount control system generates the setting value of feed-regulating valve aperture according to module feed-water quality flow deviation, is adjusted by adjusting water supply The aperture of valve realizes the control of module feedwater flow.
4. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 3 with base load operation, Be characterized in that: the module feed-water quality flow deviation is set by module feed-water quality flow measurements and module feed-water quality flow Definite value determine, and module feed-water quality flow setting value by reactor capability dispensing controller according to network load setting value and hair Electric load measured value generates.
5. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 4 with base load operation, It is characterized in that: comprising main steam pressure control system, main steam pressure control system in the main steam pressure feedback control loop System generates the setting value of main steam control valve aperture according to main steam pressure deviation, by adjusting the aperture of main steam control valve, realizes The control of main steam pressure.
6. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 5 with base load operation, Be characterized in that: the main steam pressure deviation is determined by main steam pressure measured value and main steam pressure setting value, and main steam Pressure set points are generated by reactor capability dispensing controller according to network load setting value and generation load measured value.
7. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 6 with base load operation, Be characterized in that: the main feedwater flow feedback control loop includes main feedwater flow control system, main feedwater flow control system The setting value that speed of feedwater is generated according to main feed-water quality flow deviation realizes main feedwater flow by adjusting speed of feedwater Control.
8. intermodule Coordinated Control Scheme of the multi-module type nuclear power station according to claim 7 with base load operation, Be characterized in that: the main feed-water quality flow deviation is determined by main feed-water quality flow setting value and main feed-water quality flow measurements It is fixed, and main feed-water quality flow setting value is surveyed by reactor capability dispensing controller according to network load setting value and generation load Magnitude generates.
CN201710487736.XA 2017-06-23 2017-06-23 Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation Pending CN109116722A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710487736.XA CN109116722A (en) 2017-06-23 2017-06-23 Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710487736.XA CN109116722A (en) 2017-06-23 2017-06-23 Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation

Publications (1)

Publication Number Publication Date
CN109116722A true CN109116722A (en) 2019-01-01

Family

ID=64732096

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201710487736.XA Pending CN109116722A (en) 2017-06-23 2017-06-23 Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation

Country Status (1)

Country Link
CN (1) CN109116722A (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111780089A (en) * 2020-07-20 2020-10-16 中国核动力研究设计院 Water supply control method and system for once-through steam generator
CN112420231A (en) * 2020-11-20 2021-02-26 西安热工研究院有限公司 Method for controlling outlet temperature of direct-flow steam generator of nuclear power station
CN112682770A (en) * 2020-12-25 2021-04-20 中广核研究院有限公司 Pressure control method and system for through-flow steam generator

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN88101263A (en) * 1987-03-13 1988-09-21 株式会社日立制作所 natural circulation reactor power control method and device
CN1577636A (en) * 2003-07-19 2005-02-09 韩国电力技术株式会社 Water supply control system and control method considering pressure drop of water supply control valve in nuclear power station
US6886502B1 (en) * 2004-06-23 2005-05-03 Westinghouse Electric Company Llc Method for controlling steam generators
CN103867456A (en) * 2012-12-12 2014-06-18 中广核工程有限公司 Control system and control method for regulating rotation speed of electrically driven feed pump of nuclear power station
CN106297925A (en) * 2016-07-28 2017-01-04 董哲 The water-supply scheme of a kind of multi-module type HTGR Nuclear Power Plant, dynamic model and regulation and control method

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN88101263A (en) * 1987-03-13 1988-09-21 株式会社日立制作所 natural circulation reactor power control method and device
CN1577636A (en) * 2003-07-19 2005-02-09 韩国电力技术株式会社 Water supply control system and control method considering pressure drop of water supply control valve in nuclear power station
US6886502B1 (en) * 2004-06-23 2005-05-03 Westinghouse Electric Company Llc Method for controlling steam generators
CN103867456A (en) * 2012-12-12 2014-06-18 中广核工程有限公司 Control system and control method for regulating rotation speed of electrically driven feed pump of nuclear power station
CN106297925A (en) * 2016-07-28 2017-01-04 董哲 The water-supply scheme of a kind of multi-module type HTGR Nuclear Power Plant, dynamic model and regulation and control method

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
ZHE DONG: "Coordination Control of SMR-Based NSSS Modules Integrated by Feedwater Distribution", 《TRANSACTIONS ON NUCLEAR SCIENCE》 *
李翔等: "核电站电动给水泵转速控制系统建模与仿真", 《控制工程》 *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111780089A (en) * 2020-07-20 2020-10-16 中国核动力研究设计院 Water supply control method and system for once-through steam generator
CN112420231A (en) * 2020-11-20 2021-02-26 西安热工研究院有限公司 Method for controlling outlet temperature of direct-flow steam generator of nuclear power station
CN112682770A (en) * 2020-12-25 2021-04-20 中广核研究院有限公司 Pressure control method and system for through-flow steam generator

Similar Documents

Publication Publication Date Title
Guo et al. Stability performance for primary frequency regulation of hydro-turbine governing system with surge tank
CN102279901A (en) Modeling method specific to third generation pressurized water reactor nuclear power generating unit
CN102543232B (en) Combined method for controlling water level and pressure of voltage stabilizer for nuclear power plant of pressurized water reactor
Perillo et al. Control and instrumentation strategies for multi-modular integral nuclear reactor systems
CN109116722A (en) Intermodule Coordinated Control Scheme of the multi-module type nuclear power station with base load operation
Wu et al. A load following control strategy for Chinese modular high-temperature gas-cooled reactor HTR-PM
Dong et al. Automatic generation control for the flexible operation of multimodular high temperature gas-cooled reactor plants
Dong et al. Nonlinear observer-based feedback dissipation load-following control for nuclear reactors
Wang et al. A fuzzy fault accommodation method for nuclear power plants under actuator stuck faults
Sabir et al. Load-frequency control with multimodule small modular reactor configuration: Modeling and dynamic analysis
Dong et al. Saturated output feedback dissipation steam temperature control for the OTSG of MHTGRs
Sun et al. Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink
Zhao et al. Multi-objective optimization of marine nuclear power secondary circuit system based on improved multi-objective particle swarm optimization algorithm
Lu et al. Power-heat conversion coordinated control of combined-cycle gas turbine with thermal energy storage in district heating network
Li et al. Operation and control simulation of a modular high temperature gas cooled reactor nuclear power plant
Arda et al. Implementing a pressurized water reactor nuclear power plant model into grid simulations
Wang et al. A feasibility study of load-follow operation without boron adjustment for CPR1000
CN108931928A (en) A kind of supercritical unit participates in the emulation mode for the two district system frequency modulation that wind power dissolves
Sun et al. Control strategy study for once-through direct cycle Canadian SCWRs
Wu et al. A feedforward-feedback-based reactor power decoupling control strategy for multi-modular nuclear power plants
Ping et al. Model simplification of nuclear power plant for power system dynamic simulation
Arda et al. Development of a linearized model of a pressurized water reactor generating station for power system dynamic simulations
Mahfudin et al. Auto-tuning pid controller for nuscale nuclear reactor using point reactor kinetics model simulator
Jiang et al. Modeling and Simulation of Secondary Loop Systems of a Pressurized Water Reactor Based on the 3KEYMASTER Platform
Yang et al. DYNAMIC ANALYSIS OF A SMALL PRESSURIZED WATER REACTOR BASED ON ITS TRANSFER FUNCTION

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination