CN106531268B - Link arrangement method for nuclear power plant digital accident program - Google Patents

Link arrangement method for nuclear power plant digital accident program Download PDF

Info

Publication number
CN106531268B
CN106531268B CN201610911043.4A CN201610911043A CN106531268B CN 106531268 B CN106531268 B CN 106531268B CN 201610911043 A CN201610911043 A CN 201610911043A CN 106531268 B CN106531268 B CN 106531268B
Authority
CN
China
Prior art keywords
accident
program
link arrangement
power plant
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.)
Active
Application number
CN201610911043.4A
Other languages
Chinese (zh)
Other versions
CN106531268A (en
Inventor
易珂
唐涛
张莉
孙涛
杨晓燕
高超
徐钊
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.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
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 China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN201610911043.4A priority Critical patent/CN106531268B/en
Publication of CN106531268A publication Critical patent/CN106531268A/en
Application granted granted Critical
Publication of CN106531268B publication Critical patent/CN106531268B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/008Man-machine interface, e.g. control room layout
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/04Safety arrangements
    • G21D3/06Safety arrangements responsive to faults within the plant
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Testing And Monitoring For Control Systems (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention relates to a link arrangement method for a nuclear power plant digital accident program, which comprises the steps of firstly analyzing information contained in the accident program to form an accident program function list; classifying accident program function lists according to main control state parameters in the nuclear power plant accident program, and designing corresponding human-computer interface function modules according to the function class lists; performing link arrangement on the human-computer interface functional module to form an initial version digital accident program with links; calculating the misoperation probability of an operator in an initial digital accident program, optimizing the link arrangement, and iteratively calculating the optimized misoperation probability until the optimized misoperation probability meets the design standard; and finally, optimizing the link arrangement and display mode in the accident program with complicated information. The invention can ensure that the information display and recording functions in the accident program are reasonable and scientific, reduce the burden of operators, further reduce the misoperation risk and ensure the accuracy and the rapid accessibility of accident treatment.

Description

Link arrangement method for nuclear power plant digital accident program
Technical Field
The invention belongs to the technical field of nuclear power design, and particularly relates to a link arrangement method for a digital accident program of a nuclear power plant.
Background
Under the accident condition of a pressurized water reactor nuclear power plant, an operator needs to use an accident operation program. An accident operation program (EOP) and measures thereof belong to the third defense line of the depth defense principle of a nuclear power plant, and are means for relieving accidents and limiting the consequences of the accidents.
At present, unlike a nuclear power plant using a traditional main Control room, a newly-built nuclear power plant adopts a Digital accident implementation program on the basis of a full Digital Control System (DCS). The scientific and reasonable arrangement of the digital accident program link is beneficial to building an excellent human-computer interface, so that the operator can be ensured to execute the accident program on the DCS more quickly and accurately under the accident condition.
When the nuclear power plant has an accident, the method for timely and accurately acquiring the power plant information required by the operator has important significance for relieving the accident and accurately and quickly processing the accident. Because the nuclear power plant is a huge system project and the related information is complicated and is updated rapidly, the design meeting the human factor requirements is helpful for operators to acquire the required important information of the nuclear power plant conveniently and rapidly.
For a nuclear power plant with digitalized display and operation means in a master control room, a digitalized auxiliary information control needs to be designed reasonably, so that a newly-built digitalized nuclear power plant can provide various and huge auxiliary information display and recording functions for an operator in a very flexible manner. Information in the nuclear power plant DCS is mostly displayed according to subsystems. The requirements of simultaneously monitoring and acquiring or recording a plurality of key auxiliary information during accident handling cannot be met, and the advantages of the DCS are not fully embodied.
Disclosure of Invention
The invention aims to provide a link arrangement method for a digital accident program of a nuclear power plant aiming at the defects of the prior art, so that the advantages of a digital instrument control system are fully utilized, key information related in the process of executing an accident handling program is provided for an operator, and the safety and the reliability of post-accident handling of the nuclear power plant are improved.
The technical scheme of the invention is as follows: a link arrangement method for a nuclear power plant digital accident program comprises the following steps:
(1) analyzing and sorting information contained in the accident program to form an accident program function list;
(2) classifying accident program function lists aiming at all main control state parameters related in the accident program of the nuclear power plant to form different function class lists;
(3) designing a corresponding digital man-machine interface functional module aiming at each function category list;
(4) determining the arrangement of the digital man-machine interface functional module link in the accident program to form an initial version digital accident program with links;
(5) determining the misoperation probability of an operator in an initial version digital accident program with links through human factor analysis probability calculation, and counting the links with higher misoperation probability and an accident handling stage; comprehensively considering factors of misoperation probability, link arrangement, corresponding information association degree and personnel operation time, optimizing the link arrangement in the accident program, and iteratively calculating the optimized misoperation probability of the operator until the design standard is met;
(6) and optimally arranging a link arrangement mode and a display mode in an accident program with excessively complicated information to meet the use habit of an operator.
Further, in the above-mentioned link arrangement method for the digitized accident program of the nuclear power plant, the accident program function list in step (1) includes equipment including a reactor coolant system main pump, a main spray valve, a potentiostat level gauge and a loop pressure gauge; a chemical and volume control system regulating valve, an upper charging pump and a volume control box; a boron pump, a regulating valve and a flowmeter of a reactor boron and water supply system.
Further, in the link arrangement method for the digitized accident procedure of the nuclear power plant, the main control state parameters in the step (2) include the water level of the voltage stabilizer, the pressure of the primary loop and the boron concentration.
Furthermore, according to the link arrangement method for the digital accident program of the nuclear power plant, in the step (3), the water level of the voltage stabilizer, the pressure of the loop and the boron concentration information are controlled and monitored in all the accident programs, and the corresponding digital man-machine interface functional modules for controlling the water level of the voltage stabilizer, controlling the pressure of the loop and controlling the boron concentration are designed; and further combines the loop pressure control and the water level control of the pressure stabilizer into a functional module.
Further, in the link arrangement method for the digitized accident program of the nuclear power plant as described above, the optimizing arrangement in the step (6) includes:
analyzing the occurrence frequency, operation importance and operation association degree of system equipment in all accident programs, and determining relatively important links which must be concentrated under the condition of excessively complicated information so as to ensure the rapid accessibility and accuracy in the accident handling process;
the link arrangement should be related to the relevant operation and monitoring information positions in the accident program so as to reduce the misoperation risk of operators and improve the reliability of accident handling;
the arrangement of the individual links should take into account both the experience feedback and the operating habits of the operator.
The invention has the following beneficial effects:
1. according to the invention, the man-machine interface module of the nuclear power plant digital accident program is determined through analysis, and complicated information is analyzed and classified. The information display and recording functions are reasonable and scientific, the burden of an operator is reduced, the misoperation risk is reduced, and the accuracy and the rapid accessibility of accident handling are ensured.
2. The iterative calculation method of the link arrangement adopted in step (5) of the invention helps to ensure that the probability of operator misoperation caused by the link arrangement in the accident program is sufficiently low. The optimization method in the step (6) can enable the information arrangement mode and the information display mode to meet the use habit of an operator, thereby ensuring that the operator can be quickly and accurately positioned, and enabling the human-computer interface to be scientific and reasonable.
Drawings
FIG. 1 is a flow chart of a method of the present invention;
FIG. 2 is a schematic diagram of a link arrangement of an accident program in the embodiment.
Detailed Description
The invention is described in detail below with reference to the figures and examples.
In the event of an accident, the operator brings the reactor to a safe state according to the requirements of the accident operation program. Since there is some uncertainty about what may happen in this process, the operator may need to view and record key auxiliary information at any time to help him know the current state of the unit and help him to take better action.
The digital accident program of the nuclear power plant has the disadvantages of complex information quantity related to the execution process, various system functions, more important parameters related to the unit state and wider distributed system. If the subsystem display function is called to realize when the information needs to be searched, the operation is complex and the operation efficiency of an operator under the accident condition is reduced. In addition, too many frequently called subsystem display functions will require the operator to be skilled in mastering the information in each subsystem display function, increasing the operator burden and the risk of misoperation.
From the operation perspective, the invention provides a link arrangement method of a digital accident program in a nuclear power plant accident state, as shown in fig. 1, which specifically comprises the following steps:
(1) analyzing a list of accident procedure functions
The nuclear power plant accident program is a relatively complex system which can deal with and relieve design basis accidents, part over-design basis accidents and serious accidents which may occur in a nuclear power plant. Each accident program contains a large amount of information, which needs to be analyzed and collated to form an accident program function list.
(2) Accident program function classification
And (2) determining different function type lists aiming at each main control state parameter of the nuclear power plant according to the design of the nuclear power plant control system and the accident program function list determined in the step (1). And determining the nuclear plant control parameters and the function types corresponding to the operation and monitoring information related in each accident program.
(3) Implementation of accident handling function list digitalized man-machine interface
And (3) according to the list of different function types determined in the step (2), combining accident analysis, system design and human factor analysis to realize a corresponding digital man-machine interface. And optimizing and sorting the digitalized human-computer interfaces of the accident handling function lists corresponding to the main control state parameters of each nuclear power plant to form a certain number of function modules, so that the accident procedures can be conveniently called.
(4) Link arrangement for accident programs
And (4) determining the arrangement of the functional module links in the accident program based on the results obtained in the step (2) and the step (3), and forming an initial version of the digital accident program with the links.
(5) Optimization of link placement and iterative computation of probability of maloperation
And determining the misoperation probability of an operator with a linked initial version digital accident program through human factor analysis probability calculation, and counting the links with higher misoperation probability and the accident handling stage. And comprehensively considering factors such as misoperation probability, link arrangement and corresponding information association degree, personnel operation time (including search time, operation time and the like), optimizing the link arrangement in the accident program, and iteratively calculating the misoperation probability until the relevant standard is met.
(6) Link placement verification and optimization
The information on a single digital accident program is more, complex in type and different in importance, so that the link arrangement in the program needs to be optimized:
and analyzing the occurrence frequency, the operation importance and the operation association degree of the system equipment in all accident programs. In the case of excessively complex information, it is determined that relatively important links must be concentrated to ensure rapid accessibility and accuracy in the incident handling process.
The link connection should be clear and obvious in arrangement, and an operator can conveniently and quickly position the link connection. The arrangement should be related to the relevant operation and monitoring information position in the accident program to reduce the misoperation risk of operators and improve the reliability of accident handling.
The arrangement of the individual links should take into account both the experience feedback of the operator and the operating habits.
Examples
1. Analyzing a list of accident procedure functions
The operation contents of the operation regulations of a certain accident in the power station are analyzed and collated one by one, and the relevant information in the operator of the master control room is aimed at. The accident program function list mainly related to comprises an electric heater of a reactor coolant system voltage stabilizer, a safety valve of the voltage stabilizer, an auxiliary spray valve of the voltage stabilizer, a liquid level meter of the voltage stabilizer, a loop pressure gauge and a loop thermometer; equipment cooling water system pump, regulating valve, flowmeter; important service water system pumps, regulating valves and flow meters; a containment pressure gauge and the like.
2. Accident program function classification
And determining the corresponding main state control parameters of the nuclear power plant by combining the function list determined in the previous step and the corresponding accident program: the water level of the voltage stabilizer, the pressure of a primary circuit, the temperature of the primary circuit and the pressure of a containment vessel. And sorting and arranging the determined function lists respectively.
3. Human-machine interface implementation
And (3) corresponding man-machine interface functional modules of the voltage stabilizer water level control, the primary circuit pressure control, the primary circuit temperature control, the containment pressure monitoring and the like are designed by combining information of controlling and monitoring the voltage stabilizer water level, the primary circuit pressure and temperature, the containment pressure and the like in all accident programs. As the loop pressure control and the pressurizer water level control function list has a certain content repetition, the human-computer interface function modules required to be familiar by an operator are compressed as much as possible in view of the purpose of reducing the burden of the operator, and the loop pressure control and the pressurizer water level control are combined into one function module. A functional module is designed for loop temperature control.
4. Link arrangement for accident programs
And determining the arrangement of the functional module link by combining the arrangement conditions of the loop pressure control, the water level control of the voltage stabilizer, the loop temperature control and the containment pressure monitoring information in the corresponding accident program in the example.
5. Iterative computation of operator misoperation probability
And comprehensively considering factors of all aspects such as misoperation probability, link arrangement, corresponding information association degree, personnel operation time and the like, optimizing the link arrangement in the accident program, and iteratively calculating the misoperation probability until a link arrangement scheme meeting the standard requirement is obtained.
6. Link placement verification and optimization
For the link arrangement scheme obtained by the analysis and design, the information in the display function is optimized by combining the factors of system design characteristics, a function analysis list, the importance and operation sequence of operation information, operation experience feedback and the like, and finally the link arrangement of the accident program is analyzed and designed, as shown in fig. 2.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.

Claims (5)

1. A link arrangement method for a nuclear power plant digital accident program comprises the following steps:
(1) analyzing and sorting information contained in the accident program to form an accident program function list;
(2) classifying accident program function lists aiming at all main control state parameters related in the accident program of the nuclear power plant to form different function class lists;
(3) designing a corresponding digital man-machine interface functional module aiming at each function category list;
(4) determining the arrangement of the digital man-machine interface functional module link in the accident program to form an initial version digital accident program with links;
(5) determining the misoperation probability of an operator in an initial version digital accident program with links through human factor analysis probability calculation, and counting the links with higher misoperation probability and an accident handling stage; comprehensively considering factors of misoperation probability, link arrangement, corresponding information association degree and personnel operation time, optimizing the link arrangement in the accident program, and iteratively calculating the optimized misoperation probability of the operator until the design standard is met;
(6) and optimally arranging a link arrangement mode and a display mode in an accident program with excessively complicated information to meet the use habit of an operator.
2. The link arrangement method for the digitized accident procedure of nuclear power plant of claim 1, characterized in that: the accident program function list in the step (1) comprises equipment including a reactor coolant system main pump, a main spray valve, a voltage stabilizer liquid level meter and a loop pressure gauge; a chemical and volume control system regulating valve, an upper charging pump and a volume control box; a boron pump, a regulating valve and a flowmeter of a reactor boron and water supply system.
3. The link arrangement method for a digitized accident procedure of a nuclear power plant according to claim 1 or 2, characterized in that: the main control state parameters in the step (2) comprise the water level of the voltage stabilizer, the pressure of a loop and the boron concentration.
4. A link arrangement method for a digitized accident procedure of a nuclear power plant according to claim 3, characterized in that: combining the water level, loop pressure and boron concentration information of the voltage stabilizer in all accident programs, and designing corresponding digital human-computer interface functional modules for water level control, loop pressure control and boron concentration control of the voltage stabilizer; and further combines the loop pressure control and the water level control of the pressure stabilizer into a functional module.
5. The link arrangement method for the digitized accident procedure of nuclear power plant of claim 1, characterized in that: the optimizing arrangement in the step (6) comprises:
analyzing the occurrence frequency, operation importance and operation association degree of system equipment in all accident programs, and determining relatively important links which must be concentrated under the condition of excessively complicated information so as to ensure the rapid accessibility and accuracy in the accident handling process;
the link arrangement should be related to the relevant operation and monitoring information positions in the accident program so as to reduce the misoperation risk of operators and improve the reliability of accident handling;
the arrangement of the individual links should take into account both the experience feedback and the operating habits of the operator.
CN201610911043.4A 2016-10-19 2016-10-19 Link arrangement method for nuclear power plant digital accident program Active CN106531268B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201610911043.4A CN106531268B (en) 2016-10-19 2016-10-19 Link arrangement method for nuclear power plant digital accident program

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201610911043.4A CN106531268B (en) 2016-10-19 2016-10-19 Link arrangement method for nuclear power plant digital accident program

Publications (2)

Publication Number Publication Date
CN106531268A CN106531268A (en) 2017-03-22
CN106531268B true CN106531268B (en) 2021-09-24

Family

ID=58332764

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201610911043.4A Active CN106531268B (en) 2016-10-19 2016-10-19 Link arrangement method for nuclear power plant digital accident program

Country Status (1)

Country Link
CN (1) CN106531268B (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108470592B (en) * 2018-02-28 2021-04-30 中国核电工程有限公司 Post-accident expansion application method for nuclear power plant system
CN108757484B (en) * 2018-05-25 2020-06-05 中广核工程有限公司 Oil charging and pumping loop control system and method for nuclear power plant

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101105820A (en) * 2007-08-23 2008-01-16 上海交通大学 Electrified wire netting layout computer auxiliary decision-making support system
CN102156449A (en) * 2010-12-10 2011-08-17 中国广东核电集团有限公司 Method and system for digitalizing overall grogram of nuclear power plant and digital control system (DCS) control system
CN103198231A (en) * 2013-04-23 2013-07-10 湖南工学院 Method and system for judging reliability of man-machine interfaces of DCS (digital control system) by means of HRA (human reliability analysis)
CN103474116A (en) * 2013-08-21 2013-12-25 中国核电工程有限公司 Function analysis method for operational control under accident condition of nuclear plant with digital human machine interface
CN103676896A (en) * 2013-12-20 2014-03-26 中广核核电运营有限公司 Nuclear power plant digital control room man-machine interface improvement method
CN104488036A (en) * 2012-04-18 2015-04-01 巴布科克和威尔科克斯M能量股份有限公司 Control room for nuclear power plant
CN105551550A (en) * 2015-12-15 2016-05-04 中广核工程有限公司 Intelligent accident handling rule operating method and system of nuclear power plant

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9251920B2 (en) * 2012-04-11 2016-02-02 Ge-Hitachi Nuclear Energy America Llc In-situ and external nuclear reactor severe accident temperature and water level probes

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101105820A (en) * 2007-08-23 2008-01-16 上海交通大学 Electrified wire netting layout computer auxiliary decision-making support system
CN102156449A (en) * 2010-12-10 2011-08-17 中国广东核电集团有限公司 Method and system for digitalizing overall grogram of nuclear power plant and digital control system (DCS) control system
CN104488036A (en) * 2012-04-18 2015-04-01 巴布科克和威尔科克斯M能量股份有限公司 Control room for nuclear power plant
CN103198231A (en) * 2013-04-23 2013-07-10 湖南工学院 Method and system for judging reliability of man-machine interfaces of DCS (digital control system) by means of HRA (human reliability analysis)
CN103474116A (en) * 2013-08-21 2013-12-25 中国核电工程有限公司 Function analysis method for operational control under accident condition of nuclear plant with digital human machine interface
CN103676896A (en) * 2013-12-20 2014-03-26 中广核核电运营有限公司 Nuclear power plant digital control room man-machine interface improvement method
CN105551550A (en) * 2015-12-15 2016-05-04 中广核工程有限公司 Intelligent accident handling rule operating method and system of nuclear power plant

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
《核电站安全级DCS应用软件设计过程浅析》;郑伟智;《自动化仪表》;20140228;第53-57页 *

Also Published As

Publication number Publication date
CN106531268A (en) 2017-03-22

Similar Documents

Publication Publication Date Title
US20120109618A1 (en) Accident parameter identification method for severe accidents
CN106531268B (en) Link arrangement method for nuclear power plant digital accident program
Jang et al. Human error and the associated recovery probabilities for soft control being used in the advanced MCRs of NPPs
CN110739091A (en) nuclear power plant subcritical degree direct measurement system, hardware platform and measurement method
CN108009722B (en) Risk-aware nuclear facility reliability evaluation system and method
Kang et al. Concept of an intelligent operator support system for initial emergency responses in nuclear power plants
Nayak et al. A review: passive system reliability analysis–accomplishments and unresolved issues
CN106547236A (en) A kind of nuclear power plant digitizes the method for designing of accident program elements
CN111354497B (en) Nuclear power station breach accident information diagnosis method
Park et al. Use of a big data mining technique to extract relative importance of performance shaping factors from event investigation reports
Cho et al. Exhaustive test cases for the software reliability of safety-critical digital systems in nuclear power plants
CN110070269B (en) Management optimization method for equipment in post-processing facility based on risk guidance
Muhlheim et al. Status Report on Regulatory Criteria Applicable to the Use of Digital Twins
Wu et al. Development, verification and validation of an FPGA-based core heat removal protection system for a PWR
Wang The human reliability analysis in level 2 PSA using SPAR-H method
Aldemir et al. Methodologies for the probabilistic risk assessment of digital reactor protection and control systems
CN110783007B (en) Reactor control room system
Lew et al. Computerized operator support system for nuclear power plant hybrid main control room
CN112382426B (en) Method for distributing function arrangement of backup disc of digital nuclear power plant
CN114334194B (en) High-temperature gas cooled reactor helium gas leakage early warning method, device, equipment and storage medium
CN106548282B (en) Nuclear power plant debugging risk control method and device
WO2015151267A1 (en) Device for supporting operations at time of plant accident
Mercurio Discrete dynamic event tree modeling and analysis of nuclear power plant crews for safety assessment
CN105093939B (en) Building control system design and commissioning device and method
Mazurok et al. Analysis of existing thermal-hydraulic analysis methodologies in the framework of resource extension of reactor pressure vessels

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant