CN110991884A - Fatigue monitoring and service life assessment system for nuclear power plant - Google Patents
Fatigue monitoring and service life assessment system for nuclear power plant Download PDFInfo
- Publication number
- CN110991884A CN110991884A CN201911221098.2A CN201911221098A CN110991884A CN 110991884 A CN110991884 A CN 110991884A CN 201911221098 A CN201911221098 A CN 201911221098A CN 110991884 A CN110991884 A CN 110991884A
- Authority
- CN
- China
- Prior art keywords
- data
- database
- fatigue
- server
- power plant
- 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
Links
- 238000012544 monitoring process Methods 0.000 title claims abstract description 78
- 238000000034 method Methods 0.000 claims abstract description 42
- 238000007726 management method Methods 0.000 claims abstract description 20
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims abstract description 15
- 238000013500 data storage Methods 0.000 claims abstract description 7
- 238000012545 processing Methods 0.000 claims abstract description 7
- 238000009472 formulation Methods 0.000 claims abstract description 6
- 239000000203 mixture Substances 0.000 claims abstract description 6
- 238000012216 screening Methods 0.000 claims abstract description 6
- 239000002826 coolant Substances 0.000 claims abstract description 5
- 238000012795 verification Methods 0.000 claims abstract description 5
- 239000002184 metal Substances 0.000 claims abstract description 4
- 238000012360 testing method Methods 0.000 claims abstract description 4
- 230000003993 interaction Effects 0.000 claims abstract description 3
- 238000004364 calculation method Methods 0.000 claims description 34
- 239000000463 material Substances 0.000 claims description 17
- 238000004458 analytical method Methods 0.000 claims description 13
- 238000012546 transfer Methods 0.000 claims description 10
- 238000004891 communication Methods 0.000 claims description 6
- 238000004519 manufacturing process Methods 0.000 claims description 3
- 238000011084 recovery Methods 0.000 claims description 3
- 230000003068 static effect Effects 0.000 claims description 3
- 238000013480 data collection Methods 0.000 claims 1
- 238000011161 development Methods 0.000 claims 1
- 230000035945 sensitivity Effects 0.000 claims 1
- 238000011156 evaluation Methods 0.000 abstract description 11
- 238000009795 derivation Methods 0.000 abstract description 2
- 238000005259 measurement Methods 0.000 abstract 1
- 206010016256 fatigue Diseases 0.000 description 88
- 230000035882 stress Effects 0.000 description 11
- 238000010586 diagram Methods 0.000 description 8
- 230000001052 transient effect Effects 0.000 description 8
- 238000013461 design Methods 0.000 description 5
- 230000007613 environmental effect Effects 0.000 description 3
- 238000004613 tight binding model Methods 0.000 description 3
- 238000012937 correction Methods 0.000 description 2
- 230000001186 cumulative effect Effects 0.000 description 2
- 238000012805 post-processing Methods 0.000 description 2
- 238000012827 research and development Methods 0.000 description 2
- 238000009825 accumulation Methods 0.000 description 1
- 230000003044 adaptive effect Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000004590 computer program Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 238000003745 diagnosis Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000012806 monitoring device Methods 0.000 description 1
- 230000003287 optical effect Effects 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 238000010223 real-time analysis Methods 0.000 description 1
- 230000008646 thermal stress Effects 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q10/00—Administration; Management
- G06Q10/06—Resources, workflows, human or project management; Enterprise or organisation planning; Enterprise or organisation modelling
- G06Q10/063—Operations research, analysis or management
- G06Q10/0639—Performance analysis of employees; Performance analysis of enterprise or organisation operations
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06Q—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
- G06Q50/00—Information and communication technology [ICT] specially adapted for implementation of business processes of specific business sectors, e.g. utilities or tourism
- G06Q50/06—Energy or water supply
-
- 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
- Y04—INFORMATION OR COMMUNICATION TECHNOLOGIES HAVING AN IMPACT ON OTHER TECHNOLOGY AREAS
- Y04S—SYSTEMS INTEGRATING TECHNOLOGIES RELATED TO POWER NETWORK OPERATION, COMMUNICATION OR INFORMATION TECHNOLOGIES FOR IMPROVING THE ELECTRICAL POWER GENERATION, TRANSMISSION, DISTRIBUTION, MANAGEMENT OR USAGE, i.e. SMART GRIDS
- Y04S10/00—Systems supporting electrical power generation, transmission or distribution
- Y04S10/50—Systems or methods supporting the power network operation or management, involving a certain degree of interaction with the load-side end user applications
Landscapes
- Business, Economics & Management (AREA)
- Human Resources & Organizations (AREA)
- Engineering & Computer Science (AREA)
- Economics (AREA)
- Strategic Management (AREA)
- Tourism & Hospitality (AREA)
- General Physics & Mathematics (AREA)
- Health & Medical Sciences (AREA)
- Educational Administration (AREA)
- Marketing (AREA)
- Entrepreneurship & Innovation (AREA)
- Theoretical Computer Science (AREA)
- Development Economics (AREA)
- Physics & Mathematics (AREA)
- General Business, Economics & Management (AREA)
- Operations Research (AREA)
- Quality & Reliability (AREA)
- Game Theory and Decision Science (AREA)
- Public Health (AREA)
- Water Supply & Treatment (AREA)
- General Health & Medical Sciences (AREA)
- Primary Health Care (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Testing And Monitoring For Control Systems (AREA)
Abstract
The invention discloses a fatigue monitoring and service life evaluation system for a nuclear power plant, which comprises system hardware, a system platform, a calculation program and a system database, wherein the system hardware consists of a system server, a database server, a backup server and a network switch, the system platform consists of a human-computer interaction interface and a system management service system, the system management service consists of data acquisition, data storage, data processing, parameter display, data retrieval, trend display, report formulation, reference data and system management, and the calculation program consists of measurement point screening, NCR () evaluation, temperature field analytic solution, stress field analytic solution and test verification. The invention has wide monitoring range, covers all main equipment and main pipelines of a loop of the nuclear island, innovatively realizes that the temperature state of a concerned position is obtained by a model derivation method without adding hardware instrument measuring points, thereby ensuring the minimum reconstruction and the highest efficiency of an old power plant when in application. The system innovatively considers the influence of the pressurized water reactor coolant environment on metal fatigue, and meets the requirement of a nuclear safety bureau on the charging license of a power plant.
Description
Technical Field
The invention relates to the technical field of nuclear power plants, in particular to a fatigue monitoring and life assessment system for a nuclear power plant.
Background
The nuclear power plant fatigue monitoring and life evaluation system carries out monitoring and diagnosis on the positions of main equipment and pipelines of the nuclear power plant, which are at risk of fatigue damage. The fatigue monitoring system has the function of acquiring the actual operation data information on site and providing reliable and direct data and basis for fatigue evaluation work. Meanwhile, fatigue monitoring information of a loop pressure-bearing boundary of the nuclear power plant is provided to prove the damage degree of fatigue to components to a safety supervision authority, and important basis is provided for smooth passing of periodic safety examination, license continuation application and the like.
In the prior art, the fatigue monitoring coverage of a nuclear power plant is small, the influence of a pressurized water reactor coolant environment on fatigue is difficult to consider, the old power plant is difficult to modify in a hardware instrument mode, and the economic cost is increased.
Disclosure of Invention
The invention aims to solve the problems that in the prior art, the fatigue monitoring coverage of a nuclear power plant is small, the old power plant is difficult to modify in a hardware instrument mode, and the economic cost is increased, and provides a system for monitoring the fatigue and evaluating the service life of the nuclear power plant.
In order to achieve the purpose, the invention adopts the following technical scheme:
a fatigue monitoring and service life assessment system for a nuclear power plant comprises system hardware, a system platform, a calculation program and a system database, wherein the system hardware comprises a system server, a database server, a backup server and a network switch, the system platform comprises a human-computer interaction interface and system management services, the system management services comprise data acquisition, data storage, data processing, parameter display, data retrieval, trend display, report formulation, reference data and system management, the calculation program comprises measuring point screening, NCR assessment, a temperature field analysis solution, a stress field analysis solution and test verification, and the system database comprises a real-time database, a calculation database and a material database.
Preferably, the system server is used as a core server for providing various system services, the system server is connected with a plurality of client operation stations through a power plant local area network, the system server can support various data requests and function calls of the client operation stations, process and dump received data and manage system configuration parameters, and the system server is simultaneously responsible for supporting normal operation of various core computing modules.
Preferably, the database server is used as a main storage carrier of information system data, and the database server can provide all input and process parameter calls for system application, and the database server is connected with a disk array.
Preferably, the backup server is used as a data backup carrier of the database server, and provides a backup function for database data, the backup server supports a history data recovery function, and the backup server is connected with a disk array.
Preferably, the network switch is responsible for constructing a fatigue monitoring system local area network, is connected with an external system and an external network, is in data communication with the PI system, and is respectively connected with a client in the power plant local area network and a fatigue monitoring system server.
Preferably, the real-time database is used for receiving and storing process data from each unit DCS of the nuclear power plant.
Preferably, the calculation database is used to support intermediate calculation processes of the fatigue monitoring system, and the calculation database holds all intermediate calculation variables and the final calculation output.
Preferably, the material database is used for storing material parameters for supporting calculation of the fatigue monitoring system, and the data in the material database is static data, and the data in the material database is permanently stored in the database and supports updating.
Compared with the prior art, the invention has the beneficial effects that:
1. the system innovatively realizes that ' no hardware instrument measuring point is added ', ' production network operation is not influenced ', ' water environment and non-water environment fatigue are considered ', a stress coefficient method, a green function method and a transfer function method ' in mechanics are applied to online monitoring of fatigue damage of equipment and pipelines, the fatigue damage phenomenon monitoring of important equipment of a main system and the fatigue severe position of the pipeline in the pressurized water reactor environment is realized, the monitoring range is wider and wider, meanwhile, the dependence on a hardware instrument is reduced, and the economic cost is saved;
2. the fast calculation method of the transfer function based on the Green function and the Duhamet integral takes the real-time, fast and on-line calculation occupying as little computer resources as possible of the adaptive monitoring device as a criterion, saves time and improves efficiency;
3. aiming at the characteristics of a network communication interface and a database of a power plant DCS, parameters such as temperature, pressure, flow and water chemistry and variation variables such as power plant load are collected according to fatigue monitoring and life analysis and evaluation requirements and stored in a fatigue monitoring system database, the fatigue monitoring system uses original measuring points of the power plant DCS, and instruments, sensors and other equipment are not added;
4. the fatigue life analysis and evaluation software can realize the functions of stress analysis, stress classification, result post-processing and the like, and adopts a rain flow method to calculate fatigue damage, thereby having the function of finishing result evaluation according to the standard requirement. The project is designed as a software system special for the real-time analysis and evaluation work research and development of the fatigue life of the pressure-bearing component of the nuclear power plant, and the research and development work plan of the project is developed on a universal software platform such as LabVIEW graphical programming environment
5. As the primary loop pressure-bearing components of the nuclear power plant, such as a reactor pressure vessel, a steam generator, a main pipeline and the like, basically belong to cylindrical barrel structures, the analysis system can adopt an analytic method in a cylindrical coordinate system to carry out derivation and solution on a transient temperature field, a thermal stress field and a pressure stress field. For the stress concentration problem of local positions such as a connecting pipe, a through part tee joint, a bent pipe and the like, the problem is solved by the way that a cylindrical barrel structure influences the area by unit load or unit temperature difference to obtain a transfer function and the transfer function is built in service life monitoring system analysis software
6. The system comprises a fatigue calculation and evaluation module under the water environment, and after functions of stress analysis, stress classification, result post-processing and the like are realized, fatigue correction under the water environment is carried out, and EAF fatigue damage calculation and evaluation are carried out
7. The method has the functions of monitoring whether the important equipment and the pipeline of the loop operate in a design transient range, automatically judging whether the operation transient exceeds the design transient, and monitoring, counting, identifying and classifying the transient. The conclusion of the judgment should facilitate effective operational control, tracking and assessment of plant operating conditions for nuclear power plant transients
8. Implementation of transient recognition function for conditions exceeding the temperature pressure monitoring map of the main control room reactor coolant system (PT limit), the program performs "assessment of unexpected operational events" evaluation of reactor pressure vessel fracture mechanics
9. The system has an intuitive human-computer conversation interface and has the functions of data browsing, chart display, storage output and the like, the system is accessed to a local area network of a power plant, a B/S (browser/Server) framework is adopted, and different levels and professionals can access the system according to preset authorities.
Drawings
FIG. 1 is a system module calling relationship diagram of a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
FIG. 2 is a flow chart of data transfer between system modules of a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
FIG. 3 is a flowchart of a computer program for a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
FIG. 4 is a functional diagram of a fatigue monitoring system database of a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
FIG. 5 is a simplified diagram of a fatigue monitoring system architecture of a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
FIG. 6 is a detailed diagram of a fatigue monitoring system architecture of a nuclear power plant fatigue monitoring and life assessment system according to the present invention;
fig. 7 is a schematic diagram of a system management service of a nuclear power plant fatigue monitoring and life assessment system according to the present invention.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments.
Referring to fig. 1-2, a system for monitoring fatigue and evaluating life of a nuclear power plant comprises system hardware, a system platform, a calculation program and a system database, wherein the system hardware comprises a system server and a database server, the system server is used as a core server for providing various system services, the system server is connected with a plurality of client operation stations through a power plant local area network, the system server can support various data requests and function calls of the client operation stations, process and dump received data and manage system configuration parameters, the system server is simultaneously responsible for supporting normal operation of various core calculation modules, the database server is used as a main storage carrier of information system data, the database server can provide all input and process parameter calls for system application, and the database server is connected with a disk array;
the system comprises a backup server, a network switch, a PI system, a power plant local area network, a system platform, a data storage system, a data processing system, a parameter display system, a data retrieval system, a trend display system, a report formulation system, a reference data system and a system management system, wherein the backup server is used as a data backup carrier of the database server, provides a backup function for database data, supports a historical data recovery function, is connected with a disk array, is responsible for constructing a fatigue monitoring system local area network, is connected with the external system and the external network, is in data communication with the PI system, is respectively connected with a client in the power plant local area network;
the data acquisition function is used for carrying out data communication with an external system, acquiring real-time parameters from a power plant information system (PI) system, has certain stability and reliability, can support at least 1000 points of data communication capacity, and has the following functions: the fatigue monitoring system and the PI system are kept in normal operation, the fatigue monitoring system can periodically and automatically receive power plant parameters from the PI system, monitoring transient data provided by the PI system are directly adopted during calculation of the system, transient classification and statistical data are not needed, after the fatigue monitoring system fails and recovers, the fatigue monitoring system can request the power plant parameters which are not received during the system failure period from the PI system, after the PI system fails and recovers, the fatigue monitoring system can manually trigger or automatically trigger the data which are not requested during the system failure period from the PI system, and besides an automatic acquisition mode, the fatigue monitoring system also provides a method for manually importing or inputting data in batches;
the fatigue monitoring system adopts RAID technology and optical disk backup to ensure that data in the system can be completely stored when a system server fails, the data types received by the fatigue monitoring system comprise analog quantity, switching value and packing point, the fatigue monitoring system can store all received power plant data and fatigue analysis data in the whole life cycle of a monitored unit, and the data storage meets the following characteristics: the design of database capacity is considered according to 1000 points of use requirements of a fatigue monitoring system, the system provides related measures to improve the reliability and recoverability of data storage, the database considers certain expandability and expansibility, the system provides a certain dump form, the dump form comprises but is not limited to compact disc burning and the like, data processing refers to screening and processing of data of power plant parameters acquired by data acquisition, and fatigue factor calculation of each fatigue monitoring item is provided;
the output fatigue accumulation factors include: the fatigue cumulative use factor before considering the environmental fatigue, the fatigue cumulative use factor after considering the environmental fatigue, and the like. The dynamic parameter display function comprises system overview display, detailed fatigue monitoring item display and dynamic parameter display based on a process flow chart. The overall display comprises integrated display of all monitoring items, further detailed information display is carried out on fatigue monitoring items selected by a user in the detailed fatigue monitoring item display, a simplified process flow diagram is provided by a system in the process flow diagram-based dynamic parameter display, and the dynamic parameter display is arranged at a corresponding position on the process flow diagram to assist the user in better solving related parameter information;
the data retrieval function indicates that the system can provide the condition screening function to all kinds of parameters, including fatigue monitoring point, technological parameter and equipment information etc., the trend display function indicates that the system can provide diversified trend display function, include the trend display to fatigue monitoring point and the trend display of power plant's technological parameter, report customization function indicates that the system provides report output function, the template of report is customized according to the demand of the first party, reference data display function indicates that can obtain appointed relevant electronic version reference file content and information through fatigue monitoring system, be used for supporting the user to understand process flow and relevant equipment information better, system management indicates the integrated management and the configuration to fatigue monitoring system, include: and (3) permission setting: and allocating user roles and authorities, and configuring and maintaining and managing the authorities. Authority management in fatigue monitoring systems has two main roles: the method is used for setting the authority for different users or user groups to control the business process, and the other purpose is to ensure the safety of the information system through the authority management. The privilege hierarchy includes responsibility engineers and visitors;
database maintenance and management: the function can complete data backup and management functions, provide functions of creating, moving and recovering data archive files, regularly backing up the data archive files and the like, and perform backup and log management in a manual or automatic mode, wherein a user can inquire all running log information generated by a system and also can inquire operation log information of all operations performed in the system by the user, and a calculation program consists of measuring point screening, NRC evaluation, temperature field analysis solution, stress field analysis solution and test verification;
preferably, in order to ensure that the part monitored by the fatigue monitoring system is the part which is most likely to generate fatigue failure after the equipment is fatigued under the influence of the environment, the effective fatigue monitoring points of the loop equipment need to be calculated and screened. On the basis of the calculation result of NB bundling fatigue of volume III, volume 1, according to ASME B & PV specification in the earlier stage, a NUREG/CR-6909 method is adopted to calculate the accumulated fatigue use factor after considering environmental influence fatigue, and parts corresponding to the largest and the next largest accumulated fatigue use factors are selected according to different material types and are used as the basis for determining fatigue monitoring points;
second, the program should be developed to take into account and evaluate the NCR in all device manufactures. Firstly, developing work is carried out on the basis of the original design of equipment, and necessary correction is carried out on the developed fatigue monitoring system by combining the difference between the original design of the equipment and the actual condition of the equipment, so that the influence caused by treatment of non-conformity items is considered in the fatigue monitoring system;
thirdly, solving a temperature field physical equation by adopting a finite difference method, and verifying;
fourthly, solving the stress field by adopting a transfer function method, and verifying;
fifthly, fatigue pairing calculation is carried out by adopting a rain flow method, verification is carried out, the rain flow counting method can be called as a tower top method, stress-time history data recording is rotated by 90 degrees, a time coordinate axis is vertically downward, the data recording is as a series of roofs, and rainwater flows down along the roofs, so that the rain flow counting method is called as the rain flow counting method;
and sixthly, considering the influence of a pressurized water reactor coolant environment on metal fatigue, and giving out the fatigue accumulated damage condition under the water environment fatigue, wherein the system database consists of a real-time database, a calculation database and a material database, the real-time database is used for receiving and storing process data from each unit DCS of the nuclear power plant, the calculation database is used for supporting the intermediate calculation process of the fatigue life monitoring system, the calculation database stores all intermediate calculation variables and final calculation output, the material database is used for storing material parameters for supporting the calculation of the fatigue life monitoring system, the data in the material database is static data, and the data in the material database is permanently stored in the database.
The invention innovatively realizes that ' no hardware instrument measuring point is added ', ' production network operation is not influenced ', ' water environment and non-water environment fatigue are considered ', applies a stress coefficient method, a green function method and a transfer function method ' in mechanics to the online monitoring of the fatigue damage of equipment and pipelines, realizes the monitoring of the fatigue damage phenomenon of important equipment of a main system and the severe fatigue position of the pipelines in the pressurized water reactor environment, has wider and wider detection range, reduces the dependence on hardware instruments and saves the economic cost.
The above description is only for the preferred embodiment of the present invention, but the scope of the present invention is not limited thereto, and any person skilled in the art should be considered to be within the technical scope of the present invention, and the technical solutions and the inventive concepts thereof according to the present invention should be equivalent or changed within the scope of the present invention.
Claims (12)
1. A fatigue monitoring and service life assessment system for a nuclear power plant comprises system hardware, a system platform, a calculation program and a system database, and is characterized in that the system hardware comprises a system server, a database server, a backup server and a network switch, the system platform comprises a human-computer interaction interface and a system management service platform, the system management service comprises data acquisition, data storage, data processing, parameter display, data retrieval, trend display, report formulation, reference data and system management, the calculation program comprises measuring point screening, NCR assessment, temperature field analysis solution, stress field analysis solution and test verification, and the system database comprises a real-time database, a calculation database and a material database.
2. The system of claim 1, wherein the system server is a core server for providing various system services, the system server is connected to a plurality of client operation stations through a power plant lan, and the system server can support various data requests and function calls of the client operation stations, process and dump received data, and manage system configuration parameters, and is also responsible for supporting normal operation of each core computing module.
3. The system of claim 1, wherein the database server is used as a primary storage carrier for information system data, and the database server is capable of providing all inputs and process parameter calls for system applications, and the database server is connected to a disk array.
4. The system of claim 1, wherein the backup server is used as a data backup carrier of the database server, and the backup server provides a backup function for database data, the backup server supports a historical data recovery function, and the backup server is connected with a disk array.
5. The nuclear power plant fatigue monitoring and life assessment system according to claim 1, wherein the network switch is responsible for constructing a fatigue monitoring system local area network, and the network switch is connected with an external system and an external network, the network switch is in data communication with the PI system, and the network switch is respectively connected with a client in the power plant local area network and a fatigue monitoring system server.
6. The nuclear power plant fatigue monitoring and life assessment system according to claim 1, wherein said real-time database is adapted to receive and store process data from the DCS of the units of the nuclear power plant.
7. The system of claim 1, wherein the calculation database is configured to support intermediate calculation processes of the fatigue life monitoring system, and the calculation database stores all intermediate calculation variables and final calculation outputs.
8. The system of claim 1, wherein the material database is used for storing material parameters for supporting calculation of the fatigue life monitoring system, and the data in the material database is static data, and the data in the material database is permanently stored in the database.
9. The nuclear power plant fatigue monitoring and life assessment system according to claim 1, wherein the system management service is used for data collection, data storage, data processing, parameter display, data retrieval, trend display, report formulation, reference data, system management group, providing client interface friendly, easy to operate calculation, query, record and report formulation functions.
10. The system of claim 1, wherein the system computing program screens and processes data of plant parameters obtained from the data acquisition; and provides a fatigue factor calculation for each fatigue monitoring item. The development of the program should take into account and evaluate all NCRs in the manufacture of the device; solving a temperature field physical equation by adopting a finite difference method; solving the stress field by adopting a transfer function method; performing fatigue pairing calculation by adopting a rain flow method; and (4) considering the influence of the pressurized water reactor coolant environment on metal fatigue, and giving the fatigue accumulated damage condition under the water environment fatigue.
11. The system of claim 1, wherein a finite difference method is applied to solve the temperature field of the device metal in the system calculation program, so as to realize fast and accurate online calculation.
12. The system of claim 1, wherein the system is configured to solve the stress field by applying a transfer function in the system computing program, and the transfer function database is customized for each monitored site, and the database is configured to reflect the familiarity of the geometric characteristics, material characteristics, load sensitivity, and the like of the monitored site.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911221098.2A CN110991884A (en) | 2019-12-03 | 2019-12-03 | Fatigue monitoring and service life assessment system for nuclear power plant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201911221098.2A CN110991884A (en) | 2019-12-03 | 2019-12-03 | Fatigue monitoring and service life assessment system for nuclear power plant |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN110991884A true CN110991884A (en) | 2020-04-10 |
Family
ID=70089743
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201911221098.2A Pending CN110991884A (en) | 2019-12-03 | 2019-12-03 | Fatigue monitoring and service life assessment system for nuclear power plant |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110991884A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112925677A (en) * | 2021-03-10 | 2021-06-08 | 福建宁德核电有限公司 | Backup equipment, automatic backup system and method for non-safety-level DCS historical data |
| CN113219149A (en) * | 2021-04-26 | 2021-08-06 | 苏州热工研究院有限公司 | Method for evaluating environment-promoted fatigue life of metal part of nuclear power plant |
| CN114387123A (en) * | 2021-12-09 | 2022-04-22 | 中核武汉核电运行技术股份有限公司 | Data acquisition management method |
| CN116088398A (en) * | 2023-04-10 | 2023-05-09 | 中国电力工程顾问集团西南电力设计院有限公司 | Be used for wisdom prison dish alarm system of thermal power plant |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103698236A (en) * | 2013-12-10 | 2014-04-02 | 中广核工程有限公司 | Method for estimating fatigue life of pipeline of nuclear power plant |
| GB201522288D0 (en) * | 2015-11-12 | 2016-02-03 | China Nuclear Power Engineering Co Ltd And China Guangdong Nuclear Power Holding Corp | Method, server and system for surveilling core state of nuclear power plant |
| CN105448359A (en) * | 2015-12-07 | 2016-03-30 | 中广核工程有限公司 | System and method for monitoring fatigue of nuclear power plant |
| CN106198218A (en) * | 2016-07-05 | 2016-12-07 | 中国核动力研究设计院 | A kind of method of the monitoring core level pipeline fatigue using strain transducer |
| CN106653113A (en) * | 2016-10-25 | 2017-05-10 | 核动力运行研究所 | Device and method for carrying out online monitoring on fatigue life of steam generator |
-
2019
- 2019-12-03 CN CN201911221098.2A patent/CN110991884A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103698236A (en) * | 2013-12-10 | 2014-04-02 | 中广核工程有限公司 | Method for estimating fatigue life of pipeline of nuclear power plant |
| GB201522288D0 (en) * | 2015-11-12 | 2016-02-03 | China Nuclear Power Engineering Co Ltd And China Guangdong Nuclear Power Holding Corp | Method, server and system for surveilling core state of nuclear power plant |
| CN105448359A (en) * | 2015-12-07 | 2016-03-30 | 中广核工程有限公司 | System and method for monitoring fatigue of nuclear power plant |
| CN106198218A (en) * | 2016-07-05 | 2016-12-07 | 中国核动力研究设计院 | A kind of method of the monitoring core level pipeline fatigue using strain transducer |
| CN106653113A (en) * | 2016-10-25 | 2017-05-10 | 核动力运行研究所 | Device and method for carrying out online monitoring on fatigue life of steam generator |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112925677A (en) * | 2021-03-10 | 2021-06-08 | 福建宁德核电有限公司 | Backup equipment, automatic backup system and method for non-safety-level DCS historical data |
| CN113219149A (en) * | 2021-04-26 | 2021-08-06 | 苏州热工研究院有限公司 | Method for evaluating environment-promoted fatigue life of metal part of nuclear power plant |
| CN114387123A (en) * | 2021-12-09 | 2022-04-22 | 中核武汉核电运行技术股份有限公司 | Data acquisition management method |
| CN114387123B (en) * | 2021-12-09 | 2024-04-09 | 中核武汉核电运行技术股份有限公司 | Data acquisition management method |
| CN116088398A (en) * | 2023-04-10 | 2023-05-09 | 中国电力工程顾问集团西南电力设计院有限公司 | Be used for wisdom prison dish alarm system of thermal power plant |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110991884A (en) | Fatigue monitoring and service life assessment system for nuclear power plant | |
| CN108375715B (en) | Power distribution network line fault risk day prediction method and system | |
| US5311562A (en) | Plant maintenance with predictive diagnostics | |
| KR101698224B1 (en) | Building energy consumption analysis system | |
| Henry et al. | Effects of environmental temperature change on the efficiency of coal-and natural gas-fired power plants | |
| Kang et al. | Big data analytics in China's electric power industry: modern information, communication technologies, and millions of smart meters | |
| Martorell et al. | The use of maintenance indicators to evaluate the effects of maintenance programs on NPP performance and safety | |
| CN107239705A (en) | A kind of contactless industrial control system or the static leakage location of equipment and detection method | |
| Kim et al. | Application of monitoring, diagnosis, and prognosis in thermal performance analysis for nuclear power plants | |
| Wu et al. | Leakage identification in water distribution networks based on XGBoost algorithm | |
| CN112417700B (en) | Fault diagnosis system of EH oil station based on state evaluation | |
| CN101408769A (en) | On-line energy forecasting system and method based on product ARIMA model | |
| CN111563022B (en) | Centralized memory monitoring method and device | |
| CN106022978A (en) | Intelligent power plant management system | |
| JP2002251505A (en) | System for supporting water treatment work | |
| US7412430B1 (en) | Determining the quality of computer software | |
| CN117436591A (en) | Deep optimization method of photovoltaic new energy supervision platform algorithm | |
| CN112597654A (en) | MBSE-based top-level system design scheme verification, optimization and evaluation method | |
| CN114528314B (en) | Engineering construction project supervision system and method | |
| Kariniotakis et al. | Load, wind and hydro power forecasting functions of the More-Care EMS system | |
| CN109871998B (en) | Power distribution network line loss rate prediction method and device based on expert sample library | |
| CN111080068A (en) | Method and device for evaluating running state of electric energy meter | |
| CN111598296A (en) | Power load prediction method, power load prediction device, computer equipment and storage medium | |
| CN118378156B (en) | Factory station gateway metering data missing fitting optimization method and system based on historical data analysis, electronic equipment and storage medium | |
| Wu et al. | A Universal Open Architecture of Health Management System for Radars |
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 | ||
| CB02 | Change of applicant information | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
|
| WD01 | Invention patent application deemed withdrawn after publication | ||
| WD01 | Invention patent application deemed withdrawn after publication |
Application publication date: 20200410 |