CN110909505A - Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system - Google Patents

Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system Download PDF

Info

Publication number
CN110909505A
CN110909505A CN201911221070.9A CN201911221070A CN110909505A CN 110909505 A CN110909505 A CN 110909505A CN 201911221070 A CN201911221070 A CN 201911221070A CN 110909505 A CN110909505 A CN 110909505A
Authority
CN
China
Prior art keywords
temperature
power plant
transient
equipment
temperature field
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.)
Granted
Application number
CN201911221070.9A
Other languages
Chinese (zh)
Other versions
CN110909505B (en
Inventor
邓晶晶
刘畅
沈睿
张旭
殷海峰
沈小要
刘乔
李岗
粱兵兵
贺寅彪
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.)
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
Shanghai Nuclear Engineering Research and Design Institute 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 Shanghai Nuclear Engineering Research and Design Institute Co Ltd filed Critical Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority to CN201911221070.9A priority Critical patent/CN110909505B/en
Publication of CN110909505A publication Critical patent/CN110909505A/en
Application granted granted Critical
Publication of CN110909505B publication Critical patent/CN110909505B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06QINFORMATION 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
    • G06Q50/00Information and communication technology [ICT] specially adapted for implementation of business processes of specific business sectors, e.g. utilities or tourism
    • G06Q50/06Energy or water supply

Landscapes

  • Business, Economics & Management (AREA)
  • Health & Medical Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Economics (AREA)
  • Public Health (AREA)
  • Water Supply & Treatment (AREA)
  • General Health & Medical Sciences (AREA)
  • Human Resources & Organizations (AREA)
  • Marketing (AREA)
  • Primary Health Care (AREA)
  • Strategic Management (AREA)
  • Tourism & Hospitality (AREA)
  • Physics & Mathematics (AREA)
  • General Business, Economics & Management (AREA)
  • General Physics & Mathematics (AREA)
  • Theoretical Computer Science (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a transient temperature field calculation method for a nuclear power plant fatigue monitoring and life evaluation system, which reads primary loop system fluid temperature data T acquired by a digital control system of a power plant from a power plant database through a system interfacewAnd (t) as the input of transient temperature field calculation, calculating the temperature transient of the inner wall surface of the cylindrical shell or the spherical shell through a temperature field equation, and taking the temperature transient as the input of subsequent thermal stress calculation. Has the advantages that: the invention is suitable for solving the transient temperature field of nuclear power plant equipment and pipelines, and adopts the transient temperature field of a cylindrical shell or a spherical shellThe method does not need to take the temperature of the structural wall surface as calculation input, so that a temperature measuring instrument does not need to be added on the outer wall surface of loop equipment or a pipeline, the influence of a fatigue monitoring system on the design and field arrangement of a power plant is reduced, and the construction and maintenance cost of the system is reduced.

Description

Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system
Technical Field
The invention relates to the technical field of fatigue monitoring, service life assessment and operation maintenance of equipment and pipelines of a nuclear power plant, in particular to a transient temperature field calculation method of a fatigue monitoring and service life assessment system of the nuclear power plant.
Background
The nuclear power plant loop equipment and the pipeline are used as barriers for preventing reflex leakage, and the maintenance of structural integrity has important significance for ensuring the safe and stable operation of the reactor. The primary loop equipment and the pipeline work under the working conditions of high temperature and high pressure for a long time and experience complex pressure transient state and temperature transient state change, so the fatigue is one of the main failure mechanisms of the primary loop equipment and the pipeline.
The fatigue monitoring and life evaluating system for the nuclear power plant is an online monitoring system developed for monitoring the fatigue states of a loop device and a pipeline in real time, and calculates and provides a fatigue damage coefficient considering and not considering the influence of a coolant environment and a fatigue result of a sensitive part of the monitoring device and the pipeline through the acquired actual operation data information of the nuclear power plant, so that the fatigue lives of the device and the pipeline are evaluated.
For primary loop equipment and piping, thermal stress is one of the important factors that contribute to fatigue failure of the structure. Determining the transient temperature fields of the equipment and the pipeline is a key step for calculating the thermal stress in the structure, further carrying out fatigue analysis and evaluating the fatigue states of the equipment and the pipeline.
At present, a plurality of fatigue monitoring systems of the nuclear power plant are put into use abroad, wherein the fatigue monitoring systems which are used more frequently mainly comprise FatiguePro, WESTEMS, FAMOS and SACOR, and the FASTEMS is shown in a table 1. In China, except for the product (FAMOLES) for monitoring the fatigue and evaluating the service life of the nuclear power plant, the application of the same kind of product is not seen, and related patents and patent applications mainly comprise a nuclear power plant fatigue monitoring system and a method, a steam generator online fatigue life monitoring device and a method, a pipeline tee joint area online fatigue life monitoring device and a method, and a method for online monitoring the fatigue damage of nuclear-grade equipment and pipelines, which are shown in a table 2.
TABLE 1 foreign developed summary table of fatigue monitoring system of nuclear power plant
Figure BDA0002300867580000021
TABLE 2 domestic nuclear power plant fatigue monitoring system related patent summary table
Figure BDA0002300867580000022
Figure BDA0002300867580000031
In the applied monitoring system products abroad, both WESTEMSTM, FAMOS and SACOR need to be provided with thermocouples to acquire the temperature of the outer wall surface of the structure of the fatigue sensitive area, and the temperature of the outer wall surface of the structure and the temperature of the internal fluid medium are used as input to determine the structural temperature field of the fatigue evaluation position. The Fatiguepro can install thermocouples at the site of interest as required by the customer. For a power plant in service operation, a great deal of field upgrading and reconstruction are needed for installing the thermocouple, and the application cost of the fatigue monitoring system is greatly increased.
In the related patents of fatigue monitoring of the nuclear power plant in China, "a system and a method for monitoring the fatigue of the nuclear power plant" (patent 1), "a device and a method for monitoring the online fatigue life of a tee joint area of a pipeline" (patent application 3) need to arrange a temperature sensor/thermometer in a fatigue sensitive area of equipment or a pipeline, measure the temperature of the outer wall surface, and determine the temperature of the inner wall surface by taking the temperature of the outer wall surface as one of inputs.
"a steam generator online fatigue life monitoring device and method" (patent 2) need arrange the thermometer in the fatigue sensitive position of the steam generator, measure the metal wall temperature, and through the coolant temperature of primary side, secondary side saturated steam temperature and monitoring point stress component look-up table, a series of discrete temperature responses corresponding to time interval, the temperature difference between feedwater temperature and steam temperature is expanded into average temperature, linear temperature and non-linear temperature with Fourier series method to determine the thermal stress that the temperature load caused.
The patent application 4 discloses a method for monitoring fatigue damage of nuclear-grade equipment and pipelines on line, which takes fluid temperature and pressure data as input and applies a Green function and a high-dispersion temperature curve to obtain thermal stress.
The above patent 1, patent 2, and patent application 3 all relate to the arrangement of a temperature sensor/thermometer at a fatigue sensitive part of a device or a pipeline, which will change the original design, installation, and arrangement of a power plant device or a pipeline, and greatly increase the application cost of the fatigue monitoring system.
Patent 1 and patent application 3 use the metal outer wall surface temperature as one of the inputs and determine the metal inner wall surface temperature by calculation. The method needs to arrange a temperature sensor/thermometer to measure the temperature of the outer wall surface of the metal. This will change the original design, installation, arrangement of power plant equipment or pipeline, greatly increase fatigue monitoring system's application cost.
Patent 2, according to the structural characteristics of the steam generator, different methods are adopted for different fatigue sensitive parts to determine the thermal stress caused by the thermal load, and the method comprises the following steps: determining the thermal stress of the monitoring point through linear interpolation of the temperature and the stress component comparison table of the monitoring point; determining a stress of the temperature change using a series of discrete temperature responses corresponding to the time intervals; the temperature difference is decomposed into average temperature, linear temperature and nonlinear temperature by Fourier series, and then converted into corresponding thermal stress. In the methods, a temperature sensor/thermometer needs to be arranged to measure the temperature of the metal wall surface, the original design, installation and arrangement of power plant equipment need to be changed, and the application cost of the fatigue monitoring system is greatly increased. Further, none of these methods relates to a method of calculating the temperature of the metal inner wall surface.
Patent application 4 uses fluid temperature as input, and applies green's function and high-dispersion temperature curve to calculate thermal stress, and the method does not relate to a calculation method of metal inner wall surface temperature. Due to the inertia effect of heat transfer between the fluid and the metal, a certain difference exists between the temperature of the fluid and the temperature of the inner wall surface of the metal, the temperature of the fluid is directly applied to replace the temperature of the inner wall surface of the metal to calculate the thermal stress, and the accuracy of the stress calculation result is reduced.
In order to solve the problems, a transient temperature field calculation method of a nuclear power plant fatigue monitoring and life evaluation system is provided.
Disclosure of Invention
The invention aims to solve the problems in the background art and provides a transient temperature field calculation method of a nuclear power plant fatigue monitoring and life evaluation system.
In order to achieve the purpose, the invention adopts the following technical scheme: the transient temperature field calculation method of the nuclear power plant fatigue monitoring and life evaluation system comprises the following steps:
1) reading primary loop system fluid temperature data T acquired by a digital control system of a power plant from a power plant database through a system interfacew(t) storing in a system database as input for transient temperature field calculations;
2) reading a loop system fluid temperature data T from a system databasew(T) combining simulation analysis results of the design stage of the equipment and the pipeline to carry out temperature data T on the fluid of the loop system based on the positions of the equipment and pipeline fatigue monitoring evaluation points in the systemw(t) carrying out weighting processing to obtain the fluid at the fatigue monitoring and evaluating point of the equipment and the pipelineTemperature data Tw'(t);
3) Reading preset geometric parameters, material parameters and thermal parameters of a structural model of the equipment and the pipeline from a system database, wherein the geometric parameters of the structural model comprise an inner diameter Ri and an outer diameter Ro of the shell, the material parameters comprise a thermal diffusion coefficient a and a thermal conductivity coefficient lambda of the structural material, and the thermal parameters comprise a heat exchange coefficient α;
4) 2) fluid temperature data Tw' (t) and 3) the geometric parameters Ri and Ro, the material parameters a and lambda and the thermal parameters α of the structural model of the equipment or the equipment are used as input, and the transient temperature field of the equipment or the pipeline and the transient temperature equation of the shell are calculated through the transient temperature field equation of the shell:
Figure BDA0002300867580000061
Ri≤r≤Ro,t≥0
Figure BDA0002300867580000062
r=Ri,t>0
Figure BDA0002300867580000063
r=Ro,t>0
T=T0 *(r) Ri≤r≤Ro,t=0;
5) solving 4) a transient temperature field equation to obtain a structural transient temperature field T (r, T) of the shell;
6) and (4) taking r as Ri for the structure transient temperature T (r, T) to obtain a transient temperature Ti (T) for subsequent thermal stress calculation and fatigue evaluation of the system.
In the transient temperature field calculation method of the fatigue monitoring and life evaluation system of the nuclear power plant, the method for acquiring the temperature data of the fluid in the loop system in the step 1) is to actually measure the temperature of the fluid medium in the equipment or the pipeline through the thermocouple and deduce the temperature of the inner wall surface of the metal through the temperature of the fluid medium.
In the above method for calculating the transient temperature field of the fatigue monitoring and life evaluating system of the nuclear power plant, the shell structure in step 3) is a cylinder or a sphere.
In the above method for calculating the transient temperature field of the fatigue monitoring and life evaluating system of the nuclear power plant, the transient temperature in step 6) is the metal temperature of the corresponding equipment or the inner wall surface of the pipeline.
Compared with the prior art, the transient temperature field calculation method of the nuclear power plant fatigue monitoring and life evaluation system has the advantages that:
the method is suitable for solving the transient temperature field of the nuclear power plant equipment and the pipeline, adopts the transient temperature field equation of a cylindrical shell or a spherical shell, utilizes the fluid temperature data of a loop system to quickly calculate the transient temperature field, does not need the temperature of the structural wall surface as calculation input, does not need to add a temperature measuring instrument on the outer wall surface of the loop equipment or the pipeline, reduces the influence of a fatigue monitoring system on the design and the field arrangement of the power plant, and reduces the construction and maintenance cost of the system.
Drawings
FIG. 1 is a schematic flow chart of a method for calculating a transient temperature field of a fatigue monitoring and life assessment system for a nuclear power plant according to the present invention;
FIG. 2 is a schematic diagram comparing a transient temperature field calculation method and a temperature field calculation result of a finite element solution of the nuclear power plant fatigue monitoring and life evaluation system according to the present invention.
Detailed Description
The following examples are for illustrative purposes only and are not intended to limit the scope of the present invention.
Examples
Referring to fig. 1-2, a method of calculating a transient temperature field of a nuclear power plant fatigue monitoring and life assessment system includes the steps of:
1) reading primary loop system fluid temperature data T acquired by a digital control system of a power plant from a power plant database through a system interfacew(t) storing in a system database as input for transient temperature field calculations;
2) reading a loop system fluid temperature data T from a system databasew(t) equipment and duct fatigue basedThe position of the labor monitoring evaluation point in the system is combined with the simulation analysis result of the equipment and pipeline design stage to carry out the simulation analysis on the temperature data T of the fluid in the loop systemw(T) carrying out weighting processing to obtain fluid temperature data T at the fatigue monitoring and evaluating points of the equipment and the pipelinew'(t);
3) Reading preset geometric parameters, material parameters and thermal parameters of a structural model of the equipment and the pipeline from a system database, wherein the geometric parameters of the structural model comprise an inner diameter Ri and an outer diameter Ro of the shell, the material parameters comprise a thermal diffusion coefficient a and a thermal conductivity coefficient lambda of the structural material, and the thermal parameters comprise a heat exchange coefficient α;
4) 2) fluid temperature data Tw' (t) and 3) the geometric parameters Ri and Ro, the material parameters a and lambda and the thermal parameters α of the structural model of the equipment or the equipment are used as input, and the transient temperature field of the equipment or the pipeline and the transient temperature equation of the shell are calculated through the transient temperature field equation of the shell:
Figure BDA0002300867580000081
Ri≤r≤Ro,t≥0
Figure BDA0002300867580000082
r=Ri,t>0
Figure BDA0002300867580000083
r=Ro,t>0
T=T0 *(r) Ri≤r≤Ro,t=0;
5) solving 4) a transient temperature field equation to obtain a structural transient temperature field T (r, T) of the shell;
6) and (4) taking r as Ri for the structure transient temperature T (r, T) to obtain a transient temperature Ti (T) for subsequent thermal stress calculation and fatigue evaluation of the system.
The method for collecting the fluid temperature data of the loop system in the step 1) comprises the steps of actually measuring the temperature of a fluid medium in equipment or a pipeline through a thermocouple, deducing the temperature of the inner wall surface of the metal through the temperature of the fluid medium, wherein the thermocouple is a temperature measuring element commonly used in a temperature measuring instrument, directly measures the temperature, converts a temperature signal into a thermal electromotive force signal, and converts the thermal electromotive force signal into the temperature of the measured medium through an electric instrument (a secondary instrument).
The shell structure in the step 3) is a cylinder or a sphere, and the primary equipment of a loop of the nuclear power plant, such as a reactor pressure vessel and a pipeline, basically belongs to a cylindrical barrel or a spherical shell structure.
The transient temperature in the step 6) is the metal temperature of the inner wall surface of the corresponding equipment or pipeline, and is approximately the same as the metal temperature of the outer wall surface of the equipment or pipeline.
In the invention, the primary equipment of a loop of the nuclear power plant, such as a reactor pressure vessel and a pipeline, basically belongs to a cylindrical barrel or spherical shell structure, so a transient temperature field can be deduced and solved by adopting a simplified structure model and an analytic method in a cylindrical coordinate system or a spherical coordinate system.
The temperature field calculation method of the nuclear power plant fatigue monitoring and service life evaluation system is different from a traditional method based on finite element numerical simulation, or a method for deducing the temperature of the inner wall surface by actually measuring the temperature of the outer wall surface of the metal through a thermocouple, and the transient temperature calculation of the inner wall surface of the structural metal is realized by adopting a transient temperature field equation of a cylindrical shell or a spherical shell.
By the aid of the method, the temperature of the inner wall surface of the metal of the equipment or pipeline fatigue monitoring evaluation point can be quickly and accurately calculated under the condition that a temperature measuring instrument of a loop system is not added, and the method can adapt to the quick online calculation criterion of an online monitoring system, and occupies less computer resources as much as possible.
By utilizing finite element numerical simulation, the temperature distribution of the cylindrical shell along the wall thickness direction can be calculated, the finite element solution is taken as a reference solution with higher precision, and the results of the calculation method and the finite element solution are compared as shown in figure 2, so that the difference between the two is very small.
The method is suitable for solving the transient temperature field of the nuclear power plant equipment and the pipeline, adopts the transient temperature field equation of a cylindrical shell or a spherical shell, utilizes the fluid temperature data of a loop system to quickly calculate the transient temperature field, does not need the temperature of the structural wall surface as calculation input, does not need to add a temperature measuring instrument on the outer wall surface of the loop equipment or the pipeline, reduces the influence of a fatigue monitoring system on the design and the field arrangement of the power plant, and reduces the construction and maintenance cost of the system.
The above description is only for the purpose of illustrating the preferred embodiments of the present invention and is not to be construed as limiting the invention, and any modifications, equivalents, improvements and the like that fall within the spirit and principle of the present invention are intended to be included therein.

Claims (4)

1. The transient temperature field calculation method of the nuclear power plant fatigue monitoring and life evaluation system comprises the following steps:
1) reading primary loop system fluid temperature data T acquired by a digital control system of a power plant from a power plant database through a system interfacew(t) storing in a system database as input for transient temperature field calculations;
2) reading a loop system fluid temperature data T from a system databasew(T) combining simulation analysis results of the design stage of the equipment and the pipeline to carry out temperature data T on the fluid of the loop system based on the positions of the equipment and pipeline fatigue monitoring evaluation points in the systemw(T) carrying out weighting processing to obtain fluid temperature data T at the fatigue monitoring and evaluating points of the equipment and the pipelinew'(t);
3) Reading preset geometric parameters, material parameters and thermal parameters of a structural model of the equipment and the pipeline from a system database, wherein the geometric parameters of the structural model comprise an inner diameter Ri and an outer diameter Ro of the shell, the material parameters comprise a thermal diffusion coefficient a and a thermal conductivity coefficient lambda of the structural material, and the thermal parameters comprise a heat exchange coefficient α;
4) 2) fluid temperature data Tw' (t) and 3) the geometric parameters Ri and Ro, the material parameters a and lambda and the thermal parameters α of the structural model of the equipment or the equipment are used as input, and the transient temperature field of the equipment or the pipeline and the transient temperature equation of the shell are calculated through the transient temperature field equation of the shell:
Figure FDA0002300867570000011
Figure FDA0002300867570000012
Figure FDA0002300867570000013
T=T0 *(r) Ri≤r≤Ro,t=0;
5) solving 4) a transient temperature field equation to obtain a structural transient temperature field T (r, T) of the shell;
6) and (4) taking r as Ri for the structure transient temperature T (r, T) to obtain a transient temperature Ti (T) for subsequent thermal stress calculation and fatigue evaluation of the system.
2. The method for calculating the transient temperature field of the nuclear power plant fatigue monitoring and life evaluating system according to claim 1, wherein the method for collecting the temperature data of the fluid in the loop system in the step 1) is to actually measure the temperature of the fluid medium in the equipment or the pipeline through a thermocouple, and to deduce the temperature of the inner wall surface of the metal through the temperature of the fluid medium.
3. The method for calculating the transient temperature field of the nuclear power plant fatigue monitoring and life assessment system according to claim 1, wherein the shell structure in step 3) is a cylinder or a sphere.
4. The method for calculating the transient temperature field of the nuclear power plant fatigue monitoring and life span assessment system according to claim 1, wherein the transient temperature in the step 6) is the metal temperature of the corresponding equipment or the inner wall surface of the pipeline.
CN201911221070.9A 2019-12-03 2019-12-03 Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system Active CN110909505B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201911221070.9A CN110909505B (en) 2019-12-03 2019-12-03 Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201911221070.9A CN110909505B (en) 2019-12-03 2019-12-03 Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system

Publications (2)

Publication Number Publication Date
CN110909505A true CN110909505A (en) 2020-03-24
CN110909505B CN110909505B (en) 2023-03-28

Family

ID=69821697

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201911221070.9A Active CN110909505B (en) 2019-12-03 2019-12-03 Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system

Country Status (1)

Country Link
CN (1) CN110909505B (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113916698A (en) * 2021-09-28 2022-01-11 天津大学 Control system for pipeline resonance bending fatigue tester and testing method thereof
CN116415688A (en) * 2023-03-27 2023-07-11 中国科学院空间应用工程与技术中心 Online learning method and system for fluid loop state monitoring baseline model
EP4071655A4 (en) * 2021-01-08 2023-07-19 China Nuclear Power Design Company Ltd. (Shenzhen) Straight pipeline inner wall surface temperature measurement and transient identification method and computer terminal
CN117079848A (en) * 2023-10-17 2023-11-17 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method

Citations (4)

* Cited by examiner, † Cited by third party
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
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
FR3053141A1 (en) * 2016-06-23 2017-12-29 Altran Tech - Altran METHOD FOR ESTIMATING THE RESIDUAL LIFE OF PRESSURIZED EQUIPMENT
CN110472332A (en) * 2019-08-15 2019-11-19 苏州热工研究院有限公司 The evaluation method of nuclear leve pipeline fatigue damage based on wind-structure interaction

Patent Citations (4)

* Cited by examiner, † Cited by third party
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
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
FR3053141A1 (en) * 2016-06-23 2017-12-29 Altran Tech - Altran METHOD FOR ESTIMATING THE RESIDUAL LIFE OF PRESSURIZED EQUIPMENT
CN110472332A (en) * 2019-08-15 2019-11-19 苏州热工研究院有限公司 The evaluation method of nuclear leve pipeline fatigue damage based on wind-structure interaction

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
刘浪等: "单位瞬态法在核电厂疲劳监测系统中的应用", 《原子能科学技术》 *
赵传礼等: "核电厂疲劳监测系统开发方法研究", 《核动力工程》 *

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP4071655A4 (en) * 2021-01-08 2023-07-19 China Nuclear Power Design Company Ltd. (Shenzhen) Straight pipeline inner wall surface temperature measurement and transient identification method and computer terminal
CN113916698A (en) * 2021-09-28 2022-01-11 天津大学 Control system for pipeline resonance bending fatigue tester and testing method thereof
CN113916698B (en) * 2021-09-28 2023-09-26 天津大学 Control system of pipeline resonance bending fatigue testing machine and testing method thereof
CN116415688A (en) * 2023-03-27 2023-07-11 中国科学院空间应用工程与技术中心 Online learning method and system for fluid loop state monitoring baseline model
CN116415688B (en) * 2023-03-27 2023-11-03 中国科学院空间应用工程与技术中心 Online learning method and system for fluid loop state monitoring baseline model
CN117079848A (en) * 2023-10-17 2023-11-17 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method
CN117079848B (en) * 2023-10-17 2023-12-19 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method

Also Published As

Publication number Publication date
CN110909505B (en) 2023-03-28

Similar Documents

Publication Publication Date Title
CN110909505B (en) Transient temperature field calculation method of nuclear power plant fatigue monitoring and life evaluation system
US6868366B1 (en) Method for measuring piping forces acting on a turbine casing
KR101135168B1 (en) Method and system for inspecting creep and thinned damage in heat exchanger steam tube
US6678628B2 (en) Apparatus and methods for monitoring and testing coolant recirculation systems
Taler et al. Thermal stress monitoring in thick walled pressure components of steam boilers
CN110375924B (en) Power plant valve leakage quantitative evaluation system
EP2444597B1 (en) System And Method For Determining Online Stress And Life Consumption Of A Heat Recovery Steam Generator
CN106680001A (en) Pipeline three-way area on-line fatigue life monitoring device and method
US20220090948A1 (en) Two and three-dimensional model based correction of elbow tap flow measurement
KR101174469B1 (en) Life assessment method for piping
WO2024061196A1 (en) Intelligent monitoring method and system for nuclear power station steam generator
CN106092351A (en) nuclear power station pipeline inner wall temperature measuring method and device
US8948334B2 (en) System and method for testing the steam system of a boiling water reactor
Cancemi et al. Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
CN110184403B (en) Method, system, medium and equipment for evaluating working state of cooling equipment
Wang et al. Virtual Sensing for Online Fault Diagnosis of Heat Exchangers
KR101958626B1 (en) Apparatus for detecting crack of steam generator and method using thereof
Hrinchenko et al. Technical Diagnostics and Features of Measuring NPP Power Equipment Parameters
CN205262747U (en) Be used for frequently opening fast and stop combined cycle steam turbine stop valve shell life -span monitoring device
Grądziel Determination of temperature and thermal stresses distribution in power boiler elements with use inverse heat conduction method
CN111928965B (en) Rotor temperature monitoring method and device, computer equipment and storage medium
Han et al. Sensitivity analysis about transient three-dimensional IHCP with multi-parameters in an elbow pipe with thermal stratification
WO2023139927A1 (en) Plant instrumentation device and equipment deterioration monitoring system and plant maintenance optimization system provided with same
CN113591348B (en) Method for calculating three-dimensional stress of weld joint of steam-water pipeline in service of thermal power plant
Jun et al. Method for measuring temperature of inner wall surface of pipeline in nuclear power plant

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

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.

CB02 Change of applicant information
GR01 Patent grant
GR01 Patent grant