scholarly journals Flow-accelerated corrosion rate and residual life time estimation for the components of pipeline systems at nuclear power plants based on control data

2017 ◽  
Vol 2017 (4) ◽  
pp. 83-93 ◽  
Author(s):  
Valeriy Ivanovich Baranenko ◽  
Ol’ga Mihajlovna Gulina ◽  
Nikolay Leonidovich Salnikov
Keyword(s):  
Corrosion Rate ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Residual Life ◽  
Time Estimation ◽  
Life Time ◽  
Control Data ◽  
Accelerated Corrosion ◽  
Flow Accelerated Corrosion

Development of Software Package for Managing the Lifetime of Mechanical Elements of Nuclear Power Plants under Flow-Accelerated Corrosion (FAC)

2020 ◽  
Vol 11 (5) ◽  
pp. 285-295
Author(s):  
O. M. Gulina ◽  
◽  
N. L. Salnikov ◽  
V. P. Semishkin ◽  
M. N. Tipikina ◽  
...  
Keyword(s):  
Software Package ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Life Time ◽  
General Concept ◽  
Residual Lifetime ◽  
Accelerated Corrosion ◽  
Equipment And Pipelines ◽  
Flow Accelerated Corrosion

This article focuses on results of developing the system for managing the life time of equipment and pipelines of nuclear power plants (NPP). The system is designed to calculate the intensity of Flow-Accelerated Corrosion (FAC) and a residual lifetime of elements. In Russia, the development of software for calculating the speed of FAC and value of thinning of the walls of pipelines of NPP has been carried out since the early 90s of the last century. The existing version of the software package for calculating the characteristics of FAC is implemented of loosely coupled software modules (standalone programs). There is no single concept of architecture, therefore, any modernization and addition of functionality comes down to rewriting old programs or writing new programs, loosely connected with the old ones. This article contains results of research of the feasibility of implementing a software package for monitoring FAC in the form of a set of plug-in modules. This approach allows one to easily add new functionality without overwriting the existing kernel by adding or removing modules. Based on the general concept, several modules for calculating the characters of FAC and visualizing the control data have been developed.

scholarly journals Flow-accelerated corrosion rate and residual life time estimation for the components of pipeline systems at nuclear power plants based on control data

2018 ◽  
Vol 4 (1) ◽  
pp. 35-42
Author(s):  
Valery I. Baranenko ◽  
Olga M. Gulina ◽  
Nikolaj L. Salnikov
Keyword(s):  
Wall Thickness ◽  
Power Plants ◽  
Residual Life ◽  
Time Estimation ◽  
Life Time ◽  
Residual Lifetime ◽  
Operational Control ◽  
Continue Development ◽  
Accelerated Corrosion ◽  
Flow Accelerated Corrosion

As of today, large volumes of data related to non-destructive operational control are accumulated on NPPs. For ensuring safe operation of power units, optimization of scope and scheduling operational control it is necessary to continue development of guidance documents, software products, methodological guidance and operational documentation (Baranenko et al. 1998, Gulina et al. 2013, Recommendation (NSAC-202L-R4) 2013). Approaches are examined to assessment of the rate of erosion-corrosion wear (flow-accelerated corrosion - FAC) according to the data of operational control. The present study was performed based on the data of thickness gauging of different elements of pipelines of NPPs with different types of reactor. Further development of ideas exposed in (Baranenko et al. 2016) allowed revealing specific features of ECW processes on straight sections, bends and in the zones adjacent to weld joints of pipelines of NPPs equipped with VVER and RBMK reactors. Presence of the process of deposition of corrosion products on internal surfaces of pipeline walls results in the fact that residual lifetime of elements nominally increases due to deposition. However, real wall thickness under the layer of deposits is unknown just as the initial wall thickness is unknown as well. Investigation implemented in the present study is aimed at the substantiation of the methodology of calculation of FAC rate according to the data of operational control for the purpose of drawing calculation results closer to the reality keeping conservatism. Uniform approach to the assessment of FAC rate in the examined elements of pipelines was developed. Methodologies for evaluation of correction coefficients taking into account dimensional technological tolerances, special features of geometry of the element, as well as effect of deposits on the results of thickness measurements were suggested based on the data of operational control and industry standards. The implemented studies demonstrated efficiency of the developed procedures for pipeline welding zones. Analysis of known and newly developed procedures was performed for bends and ranking of these procedures according to the criterion of “conservatism of evaluation of residual lifetime” was executed. Introduction of correction coefficients allows enhancing conservatism of calculations of lifetime characteristics as compared with calculations performed on the basis of nominal values of thicknesses; the result depends on the type and dimensions of the element, its geometry, as well as on the type of reactor.

A Procedure for Determining the Safe Operation Time of Equipment and Pipelines Based on Nondestructive Testing Results

Vestnik MEI ◽  
2020 ◽  
Vol 6 (6) ◽  
pp. 11-17
Author(s):  
Dmitriy A. Kuz'min ◽  
◽  
Aleksandr Yu. Kuz'michevskiy ◽  
Artem E. Gusarov ◽  
◽  
...  
Keyword(s):  
High Pressure ◽  
Wall Thickness ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Operation Time ◽  
Safe Operation ◽  
Accelerated Corrosion ◽  
Equipment And Pipelines ◽  
Flow Accelerated Corrosion

The reliability of nuclear power plants (NPPs) has an influence on power generation safety and stability. The reliability of NPP equipment and pipelines (E&P), and the frequency of in-service inspections are directly linked with damage mechanisms and their development rates. Flow accelerated corrosion (FAC) is one of significant factors causing damages to E&P because these components experience the influence of high pressure, temperature, and high flow velocity of the inner medium. The majority of feed and steam path components made of pearlitic steels are prone to this kind of wear. The tube elements used in the coils of high pressure heaters (HPH) operating in the secondary coolant circuit of nuclear power plants equipped with a VVER-1000 reactor plant were taken as the subject of the study. The time dependences of changes in the wall thickness in HPH tube elements are studied proceeding from an analysis of statistical data of in-service nondestructive tests. A method for determining the initial state of the E&P metal wall thickness before the commencement of operation is proposed. The article presents a procedure for predicting the distribution of examined objects' wall thicknesses at different times of operation with determining the occurrence probability of damages caused by flow accelerated corrosion to calculate the time of safe operation until reaching a critical state. A function that determines the boundary of permissible values of the HPH wall thickness distributions is obtained, and it is shown that the intervals of in-service inspections can be increased from 6 years (the actual frequency of inspections) to 9 years, and the next in-service inspection is recommended to be carried out after 7.5 years of operation. A method for determining the existence of FAC-induced local thinning in the examined object has been developed. The developed approaches and obtained study results can be adapted for any pipelines prone to wall thinning to determine the frequency of in-service inspections (including an express analysis based on the results of a single nondestructive in-service test), the safe operation time, and quantitative assessment of the critical value reaching probability.

Flow Accelerated Corrosion Program in the Belgian Nuclear Power Plants

2009 ◽  
Author(s):  
Anne-Sophie Bogaert ◽  
Michel Desmet ◽  
Arnaud Gendebien
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Ultrasonic Inspection ◽  
Accelerated Corrosion ◽  
Balance Of Plant ◽  
Nuclear Plants ◽  
Set Up ◽  
Predictive Software ◽  
Flow Accelerated Corrosion

Since the Surry-accident of 1986, Electrabel and Tractebel Engineering have performed extensive ultrasonic inspection campaigns to detect pipe wall thinning due to Flow Accelerated Corrosion (FAC) in the Balance-of-Plant systems of the seven Belgian nuclear power plants. Since 2000 EPRI’s predictive software CHECWORKS is used as a means to focus future inspections on the most susceptible components. In 2005, Tractebel Engineering participated in a benchmark set-up by the Framatome Owners Group (FROG) that compared the different FAC predictive models used by the FROG members. In 2006, Electrabel and Tractebel Engineering decided to perform an assessment of the way in which the follow-up of Flow Accelerated Corrosion (FAC) is done in the Belgian nuclear plants. This paper summarizes the Flow Accelerated Corrosion program in the Belgian nuclear plants as well as some of the main aspects of the Flow Accelerated Corrosion management, including the use of a predictive software, the method of inspections and the actions taken to keep the FAC program up to date.

Development of an On-Line Ultrasonic System to Monitor Flow-Accelerated Corrosion of Piping in Nuclear Power Plants

2004 ◽  
Vol 270-273 ◽  
pp. 2232-2238 ◽  
Author(s):  
Na Young Lee ◽  
Chi Bum Bahn ◽  
Sang Geun Lee ◽  
Ji Hyun Kim ◽  
Il Soon Hwang ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Accelerated Corrosion ◽  
On Line ◽  
Flow Accelerated Corrosion

Erosion in Nuclear Piping Systems

2010 ◽  
Vol 132 (2) ◽  
Author(s):  
Harold M. Crockett ◽  
Jeffrey S. Horowitz
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Cavitation Erosion ◽  
Solid Particle Erosion ◽  
Particle Erosion ◽  
Droplet Impingement ◽  
Accelerated Corrosion ◽  
Piping Systems ◽  
Flow Accelerated Corrosion

Various mechanisms degrade components and power piping in nuclear power plants. The mechanism with the greatest consequence has been flow-accelerated corrosion (FAC). FAC has caused ruptures and leaks and has led to numerous piping replacements. United States utilities use a combination of EPRI guidance, software, and aggressive inspection programs to deal with FAC. However, current technology does not detail guidance for erosive forms of attack including, cavitation erosion, flashing erosion, droplet impingement, and solid particle erosion. These forms of degradation have caused shutdowns, and leaks have become a maintenance issue. This brief will present a description of erosive damage mechanisms found in nuclear power plants.

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