Prediction method and system for reliability of single in-service pressurized water reactor nuclear power unit
A technology of nuclear power units and pressurized water reactors, which is applied in the direction of complex mathematical operations, instruments, and data processing applications, and can solve the problems that the reliability prediction of pressurized water reactor nuclear power units cannot be applied, and there is no suitable method and system.
Active Publication Date: 2020-03-31
SHANGHAI POWER EQUIP RES INST
View PDF6 Cites 0 Cited by
- Summary
- Abstract
- Description
- Claims
- Application Information
AI Technical Summary
Problems solved by technology
Since the regular maintenance of PWR nuclear power units is completely different from that of thermal power generating units, the existing reliability prediction methods for thermal power generating units cannot be applied to the reliability prediction of PWR nuclear power units.
There is no suitable method and system available for the quantitative prediction of the reliability of a single PWR nuclear power unit in service, which is an urgent technical problem to be solved in this technical field
Method used
the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
View moreImage
Smart Image Click on the blue labels to locate them in the text.
Smart ImageViewing Examples
Examples
Experimental program
Comparison scheme
Effect test
Embodiment
[0051] Example: Unit 1 of a 1000MW single in-service pressurized water reactor nuclear power plant has been put into operation for 8 years. use figure 1 The reliability prediction system and image 3 The computer software for predicting the equivalent reliability coefficient of a single in-service PWR nuclear power unit is running on the computing server in the control center of the nuclear power plant. For the reliability prediction of this type of 1000MW single in-service pressurized water reactor nuclear power unit, the figure 2 The flow chart of the reliability prediction of a single in-service PWR nuclear power unit is shown, and the reliability prediction results of this type of 1000MW single in-service PWR nuclear power unit are obtained. Such as Figure 4 , Figure 5 and Figure 6 As shown, the 9th, 10th and 11th year of a certain type of 1000MW single in-service PWR nuclear power unit obtained by using the computer software of the reliability prediction method f...
the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More PUM
Login to View More Abstract
The invention relates to a prediction method and system for reliability of a single in-service pressurized water reactor nuclear power unit, and belongs to the technical field of nuclear power engineering. The system comprises a database server, a computing server, a man-machine interface webpage server and a user terminal browser. By using the prediction system and method provided by the invention, the equivalent available coefficient of the single in-service pressurized water reactor nuclear power unit is quantitatively predicted according to the statistical result of the reliability historical data of the single in-service pressurized water reactor nuclear power unit and the unplanned outage days and refueling overhaul days in the future years, and the reliability of the single in-service pressurized water reactor nuclear power unit is quantitatively evaluated. Computer online quantitative prediction and quantitative evaluation of the reliability of a single in-service pressurized water reactor nuclear power unit are realized, so that the reliability of the single in-service pressurized water reactor nuclear power unit is in a controlled state to ensure that the equivalent available coefficient of the single in-service pressurized water reactor nuclear power unit meets the reliability requirement of a first-class nuclear power unit.
Description
technical field [0001] The invention relates to a method and system for predicting the reliability of a single in-service pressurized water reactor nuclear power unit, belonging to the technical field of nuclear power engineering. Background technique [0002] During the use stage of nuclear power units, the statistical results of the equivalent availability coefficient of a single in-service PWR nuclear power unit can be determined by statistically analyzing the operation history data of a single in-service PWR nuclear power unit. Since 1994, the power industry has held a press conference every year to announce the statistical results of the reliability of PWR nuclear power units in service in China. However, the existing statistical methods for the reliability of in-service PWR nuclear power units cannot quantitatively predict the equivalent availability factor of a single in-service PWR nuclear power unit in the next few years during the use stage. [0003] In the prior ...
Claims
the structure of the environmentally friendly knitted fabric provided by the present invention; figure 2 Flow chart of the yarn wrapping machine for environmentally friendly knitted fabrics and storage devices; image 3 Is the parameter map of the yarn covering machine
Login to View More Application Information
Patent Timeline
Login to View More Patent Type & Authority Applications(China)
IPC IPC(8): G06F17/18G06Q10/06G06Q50/06
CPCG06F17/18G06Q10/06313G06Q10/0639G06Q50/06
Inventor 史进渊徐佳敏蒋俊林润达谭振山徐望人杨宇邓志成汪勇王家鋆
Owner SHANGHAI POWER EQUIP RES INST