scholarly journals Remaining Service Life Evaluation of Nuclear Power Plants Construction Steel Elements

2021 ◽  
Vol 1926 (1) ◽  
pp. 012050
Author(s):  
E A Bausk ◽  
V M Volchuk ◽  
O V Uzlov
Author(s):  
Nikolay A. Makhutov ◽  
Mikhail M. Gadenin ◽  
Sergey V. Maslov ◽  
Dmitry O. Reznikov ◽  
Sergey N. Pichkov ◽  
...  

2021 ◽  
Vol 313 ◽  
pp. 94-105
Author(s):  
A. Bernatskyi ◽  
V. Sydorets ◽  
O.M. Berdnikova ◽  
I. Krivtsun ◽  
O. Kushnarova

Extending the lifetime of energy facilities is extremely important today. This is especially true of nuclear power plants, the closure (or modernization) of which poses enormous financial and environmental problems. High-quality repair of reactors can significantly extend their service life. One of the critical parts is heat exchangers, the tubes of which quite often fail. Sealing, as a type of repair of heat exchanger tubes by the plugs, is promising provided that the joint quality is high. Practical experience in the use of welding to solve this problem has shown the need to search technological solutions associated with increasing the depth of penetration and reducing the area of thermal effect. The aim of the work was to develop a highly efficient technology for repair and extension of service life of heat exchangers of nuclear power plants based on the results of studying the technological features of laser welding of joints of dissimilar austenitic steels AISI 321 and AISI 316Ti in the vertical spatial position. Based on the results of the analysis of mechanical test data, visual and radiographic control, impermeability tests and metallographic studies of welded joints, the appropriate modes of laser welding of plugs have been determined. The principal causes of defects during laser welding of annular welded joints of dissimilar stainless steels are determined and techniques for their elimination and prevention of their formation are proposed. Based on the results of the research, technological recommendations for laser welding of plugs in the heat exchange tube of the collector are formulated, which significantly improves the technology of repair of steam generators of nuclear power plants and extends the service life of reactors.


Author(s):  
Georges Bezdikian

The life management of French Nuclear Power Plants is an important issue and a major stake considering the aging management assessment of the key components of the plant, both from an economic and a technical point of view. The actual life evaluation is: • The first 3-loop PWR plants have 25 years in operation, • The first 4-loop PWR plants have 19 years in operation. To optimize the best and strategic choice in order to achieve the best possible performance and to prepare the technical and economical choice and decision considering: • the mode of degradation for different components, • the industrial capacity and capability to replace or to repair components, • the life evaluation of components with time limit in operation, the French utility has organized the life management of Nuclear Plant in function of several program of knowledge on degradation mode from the large and long term experience feedback and the maintenance program for life management based on normal and periodic maintenance actions and exceptional maintenance carried out on strategic components. This paper shows the table of degradation mode and different actions engaged by utility on: • In-Service Inspection, periodic maintenance, • Alternative maintenance actions, • Exceptional program of maintenance based on several mitigation and strategic replacement of components. This paper provides the reader with an overview of how advanced information processing techniques to the improvement of in-service inspections, condition-based maintenance, and asset management.


2019 ◽  
pp. 54-62
Author(s):  
T. Bilan ◽  
I. Rezvik ◽  
O. Sakhno ◽  
O. But ◽  
S. Bogdanov

The mechanisms of cable ageing at nuclear power plants (NPPs) mainly depending on the insulation material, as well as the damaging factors affecting cables that are determined by the operating conditions are considered in the paper. The main and additional mechanisms of aging resulting from the effects of damaging factors are provided. The paper presents the main methods of cable aging management: determining the actual service life and testing using field methods and other means. The basic principles for the arrangement of cable aging management at Ukrainian NPPs, as well as the methods used to investigate the technical condition of cables, are presented. A list of mandatory lists has been defined when performing activities on cable aging management. A methodology is described for lifetime extension of cables, and conditions for extending the service life of cables that are in service are provided. A number of methods of testing cables for aging management are considered: visual inspection of insulation and measurement of crack size, discoloration, etc.; insulation hardness test; insulation chemical analysis; electrical insulation tests; tensile strength measurement; measurement of elongation at break; measurements of dielectric loss at low frequency or sweep frequency; testing by dynamic reflectometry method; AC and DC current impedance measurements. The paper presents results of separate laboratory studies for selected 1 kV representative power cables with PVC insulation of SUNPP-1, ZNPP-1 and KhNPP-2 conducted within Ukrainian NPP long-term operation, which included a stage of laboratory examination and examination of cable samples in operating conditions. The following results were obtained: dependence of VVGng 4x6 cable lifetime on operating temperature; dependence of AVVG cable lifetime on operating temperature; dependence of AVVG (a) cable lifetime on operating temperature. There are possibilities and conditions under which the use of cables within long-term operation is permissible.


2007 ◽  
Vol 120 ◽  
pp. 25-30 ◽  
Author(s):  
J.C. Kim ◽  
Jae Boong Choi ◽  
Yoon Suk Chang ◽  
Young Jin Kim ◽  
Youn Won Park ◽  
...  

While the demand on electric power is consistently increasing, public concerns and regulations for the construction of new nuclear power plants are getting restrict, and also operating nuclear power plants are gradually ageing. For this reason, the interest on lifetime extension for operating nuclear power plants by applying lifetime management system is increasing. The 40-year design life concept was originally introduced on the basis of economic and safety considerations. In other words, it was not determined by technological evaluations. Also, the transient design data which were applied for fatigue damage evaluation were overly conservative in comparison with actual transient data. Therefore, the accumulation of fatigue damage may result in a big difference between the actual data and the design data. The lifetime of nuclear power plants is mostly dependent on the fatigue life of a reactor pressure vessel, and thus, the exact evaluation of fatigue life on a reactor pressure vessel is a crucial factor in determining the extension of operating life. The purpose of this paper is to introduce a real-time fatigue monitoring system for an operating reactor pressure vessel which can be used for the lifetime extension. In order to satisfy the objectives, a web-based transient acquisition system was developed, thereby, real-time thermal-hydraulic data were reserved for 18 operating reactor pressure vessels. A series of finite element analyses was carried out to obtain the stress data due to actual transient. The fatigue life evaluation has been performed based on the stress analysis results and, finally, a web-based fatigue life evaluation system was introduced by combining analysis results and on-line monitoring system. Comparison of the stress analysis results between operating transients and design transients showed a considerable amount of benefits in terms of fatigue life. Therefore, it is anticipated that the developed web-based system can be utilized as an efficient tool for fatigue life estimation of reactor pressure vessel.


Atomic Energy ◽  
2008 ◽  
Vol 104 (3) ◽  
pp. 212-217
Author(s):  
N. S. Kostyukov ◽  
V. A. Demchuk ◽  
V. A. Okhotnikov ◽  
M. I. Muminov ◽  
Kh. B. Nurmatov

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