1 Current state the theory of forecasting and evaluating the reliability characteristics of NPP equipment.

1.1 NPP equipment life management: conceptual approach.

1.2 Operational reliability of the secondary circuit elements.

1.2.1 general characteristics secondary circuit equipment.

1.2.2 Operational reliability of the capacitor.

1.2.3 Operational reliability of HDPE and HPH.

1.2.4 SG operational reliability.

1.3 Statistical and physico-statistical approaches to the assessment of equipment life.

1.4 Analysis of resource management methods.

1.5 Conclusions on the first chapter.

2 Forecasting the service life of a nuclear power plant.

2.1 Analysis of methodological and guidance materials for assessment technical condition and residual life of the NPP EPS elements.

2.2 Level optimization problem for detecting discord in the observed random process.

2.3 Security and development issues nuclear energy Russia.

2.4 Development of an economic criterion.

2.5 Markov model of exploitation.

2.6 Conclusions on the second chapter.

3 Prediction of secondary circuit equipment resource by damage summation methods.

3.1 Limit state criteria and models of damage accumulation in the secondary circuit equipment material.

3.2 Development of a drop-impact erosion model.

3.3 Calculation of reliability characteristics of steam and water equipment

NPP under conditions of drop impact erosion.

3.4 Model of linear summation of damages in SG heat-exchange tubes.

3.5 Nonlinear damage summation model.

3.6 Influence of the measurement accuracy of the main indicators of the water-chemical regime on the calculation results.

3.7 Conclusions on the third chapter.

4 Forecasting the resource of SG heat-exchange tubes by the Kalman linear stochastic filtering method.

4.1 Analysis of operational data and problem statement.

4.2 Construction of the Kalman filter for predicting the SG resource based on the damage summation model.

4.3 Algorithm of the Kalman filter for the process of crack growth in HTPG.

4.4 The principle of constructing an optimal algorithm for SG tubular resource management based on the Kalman filter.

4.5 Conclusions on the fourth chapter.

5 Development of a method for optimizing the volume and frequency of control of NPP equipment elements subject to erosion-corrosion wear.

5.1 The problem of ECI of NPP equipment.

5.2 FEC prediction method.

5.3 ECI process model.

5.4 Developed algorithms for processing primary control data.

5.5 Results of the processing of primary control data on

5.6 Results of the processing of primary control data on

5.7 Results of processing primary control data at the Black NPP.

5.8. Results of data processing of primary control at KolNPP.

5.9 To substantiate the methodology for calculating the allowable wall thicknesses.

5.10 Conclusions on the fifth chapter.

6 Neural network model for assessing and predicting the performance of nuclear power plant equipment elements subject to erosion-corrosion wear.

6.1 Overview of ECI intensity prediction methods.

6.2 Substantiation of the use of the apparatus of neural networks for predicting the intensity of the ECI process.

6.3 Learning algorithms and neural network models.

6.4 Conceptual diagram of an intelligent system for the task of predicting the ECI.

6.5 Conclusions on section 6.

Recommended list of dissertations

• Resource management of elements of the condensate-feed path of VVER power units based on the analysis of operational data 2007, candidate of technical sciences Kornienko, Konstantin Arnoldovich

• Forecasting the resource and reliability of heat exchange equipment of power plants 2008, Candidate of Technical Sciences Deriy, Vladimir Petrovich

• Diagnostics and control of erosion and corrosion wear of pipelines and heat exchange equipment of nuclear power plants 2000, candidate of technical sciences Nemytov, Sergey Aleksandrovich

• Systematization and development of models for predicting the resource of equipment of power units of nuclear power plants 2004, candidate of technical sciences Zhiganshin, Akhmet Abbyasovich

• Increasing the reliability and service life of power equipment operating in two-phase and multi-component flows 2003, Doctor of Technical Sciences Tomarov, Grigory Valentinovich

Introduction to the thesis (part of the abstract) on the topic "Physico-statistical models of resource management of equipment of the secondary circuit of nuclear power plants"

The safety of nuclear power plants is largely determined by the reliable operation of the steam generation system and the external cooling system, consisting of steam turbine condensers and a regeneration system.

The safe operation of NPP power units and measures to extend the service life are impossible without careful observance of the rules and regulations for operation and maintenance, analysis of the effectiveness of certain control actions, development of methods for probabilistic forecasting of equipment life characteristics, as well as the introduction of modern procedures for processing monitoring data. Reviews by I.A. Tutnova, V.I. Baranenko, A.I. Arzhaeva, S.V. Evropina, works by A.F. Getman, V.P. Gorbatykh, N.B. Trunova, A.A. Tutnova and others.

But in addition to the safety condition, the operation of the power unit is also subject to the condition economic efficiency operation. These problems are considered and developed in the works of A.N. Karkhova, O.D. Kazachkovsky and others. The efficiency of electricity production largely depends on the downtime of the unit associated with preventive maintenance or elimination of the causes of NPP equipment failures. Classification of equipment important from the point of view of the impact on safety, carried out in different countries, developing nuclear power, outlined the main types of equipment that should be considered when deciding whether to extend the service life. These issues are substantively considered in the documents of the IAEA, in the works of E.M. Sigala, V.A. Ostreikovskiy and others. The influence of the selected equipment on the power supply unit factor is due to downtime due to the unreliability of this equipment. One of the main tasks in this regard is to predict the reliability characteristics of equipment and evaluate the effectiveness of control measures based on models of aging processes that limit its resource. In a large number of works devoted to the development of theoretical models of these processes, the presented models are quite complex and contain a large amount of specific data, which makes it difficult to use such models in resource prediction.

Currently, the problem of optimizing the service life of a power unit is topical, taking into account the effects of equipment metal aging and the cost of modernization measures. A feature of the task of optimizing the service life of an EB is that it is a task of individual forecasting, therefore, it is required to organize the collection and processing of initial information, justify the choice of an economic criterion, and formulate an optimization principle taking into account the economic situation during the operation of a particular EB.

Secondary circuit equipment in this regard plays special role, because it is subject to various aging processes, works in various conditions, the assigned resource, as a rule, is commensurate with the resource of the block, the replacement has a rather high cost.

The aging processes of secondary circuit equipment materials, as well as NPP equipment in general, are objective, and for timely effective resource management, it is necessary to assess the technical condition of equipment during operation and widely use diagnostic and non-destructive testing programs. These data must be processed in a timely and high-quality manner and used in predicting the resource characteristics of equipment.

Therefore, it is necessary to develop approaches, methods and algorithms for setting and solving the problem of optimizing the EB service life, developing methods for predicting the resource, taking into account various factors, the nature of the aging process and its probabilistic nature, as well as using computational procedures that make it possible to obtain effective assessments, determine the relevance of the dissertation work.

The conditions laid down in the project and determining the technical, economic and temporal aspects of the design period may differ significantly from the real ones during operation. Moreover, they can be improved by reducing damaging factors as a result of Maintenance and upgrades and therefore manage the service life.

AC (Ageing Management Program - AMP) Life Management Program (AMP) concept is based on the concept of maintaining design indicators and functions important to safety through an interconnected system of measures for maintenance and diagnostic maintenance, timely repair and modernization. Modernization should also include the introduction of new technologies for operation and repair, including those for managing nuclear power plants, which make it possible to reduce the rate of degradation of the properties and parameters of equipment, engineering systems of specific units.

Active works on the topic of life extension, (PSS) with a focus on the mechanisms of aging and measures to reduce their impact, led to the emergence of the term "management of aging", which emphasizes the controllability of the process and the possibility of active influence< со стороны эксплуатирующей организации.

Service Life Management (LMS) nuclear power plants is an integrated practice for ensuring socio-economic efficiency and safe operation, including aging management programs.

From an economic point of view, CSS is one of the essential parts of the overall methodology and practice of cost optimization in order to achieve maximum profit while maintaining competitiveness in the market of electricity producers and ensuring safety. From a technical point of view, the CSS is a set of measures to maintain or improve the safety of nuclear power plants, ensure the operability and durability of the main elements (systems) and the unit as a whole, while minimizing operating costs. Conditions for the preparation and implementation of life cycle management should be created at all stages life cycle power unit.

A brief analysis of the programs of the IAEA Member States and a general methodology for solving the problem of life extension (LAT) are given in the IAEA report "Nuclear Plant Aging and Life Extension". All programs are classified as follows:

Estimating the life of equipment that cannot be replaced;

Service life extensions or planned replacements of major components that are economically feasible;

Planning overhaul and replacement of equipment to ensure safe and reliable operation.

The main theoretical developments in this area should be:

Reliability assessment methods;

Safety assessment methods;

Methods for assessing economic efficiency;

Methods for predicting aging as a function of time.

The object of study is the equipment of the second circuit of the NPP. The subject of the study is the assessment of resource characteristics of equipment.

The purpose and objectives of the study - development theoretical foundations and applied models for assessing, predicting and managing the service life of NPP secondary circuit equipment based on statistical processing of data on operation and taking into account the mechanisms of aging processes. To achieve this goal, the following tasks are solved: 1. Analysis and systematization of operation data in terms of the impact of physical processes on aging processes of secondary circuit equipment materials and substantiation of the use of physical-statistical models for individual assessment, prediction and management of the service life of NPP secondary circuit equipment.

2. Development of methods for predicting the resource characteristics of secondary circuit equipment in the conditions of accumulation of damage from the action various processes aging of the material, taking into account their probabilistic nature.

3. Development of methods and algorithms for optimizing the service life of a power unit based on an economic criterion that takes into account the diversity of costs and results, the reliability characteristics of the unit's equipment and the cost of repairs and replacements of equipment during operation.

4. Development of methods for solving the problem of reaching the limit state by elements of NPP equipment.

5. Optimization of volumes and frequency of monitoring the technical condition of NPP secondary circuit equipment subject to erosion-corrosion wear.

6. Development of a method for predicting the intensity of the FCI process of NPP equipment elements made of pearlitic steels based on the theory of neural networks.

Research methods. The work is based on the use and development of methods for the safe operation of nuclear power plants, reliability theory, probability theory and mathematical statistics, using which the following were carried out:

Analysis of operating factors limiting the service life of NPP equipment;

Analysis of statistical data on the operability of NPP equipment;

Modeling of aging processes based on the physics of processes, experimental data and periodic monitoring data.

The scientific novelty of the work lies in the fact that, in contrast to existing approaches to determining the service life of a power unit, the proposed concept uses the formulation of the problem taking into account the effects of aging of NPP equipment, and also that methods have been developed for predicting the resource characteristics of equipment using models of physical aging processes , more information on operating parameters and measures taken to manage the service life of secondary circuit equipment nuclear power plants. When developing methods for assessing and predicting resource characteristics, a number of new theoretical results were obtained: the significance of the factors that determine the intensity of aging processes in the material, which is necessary to manage the resource of specific NPP equipment;

A probabilistic model for predicting the resource of heat exchange tubes of a steam generator based on the methods of linear and nonlinear summation of damages, taking into account the operating parameters and the type of the main aging process; asymptotic methods for solving the problem of reaching the limit state by equipment elements: in the drop impact erosion model under conditions of two-phase coolant flows, in damage summation methods in the problem of estimating the SG TOT resource;

A method for predicting the resource of a steam generator tube based on linear stochastic Kalman filtering, which makes it possible to take into account a large amount of operational data, monitoring data and research results based on mathematical models damage processes and ongoing preventive measures, which, in contrast to known methods, leads to an increase in the reliability of the forecast and the ability to qualitatively manage the resource of the tubular on the basis of the formulated principle optimal control;

A method for optimizing the volumes and frequency of control of the thickness of NPP equipment elements subject to erosion-corrosion wear, based on the proposed method for processing control data and determining the elements belonging to the EQI risk group, calculating the allowable wall thicknesses and ranking the elements according to the degree of wear and EQI rate, based on the first analysis of a large number of measurements at the Kola, Kalinin, Balakovo, Novovoronezh, Smolensk NPPs;

A neural network model for assessing and predicting the performance of equipment elements subject to erosion-corrosion wear, based on the observed parameters that determine the intensity of the ECI process, and control data, which, unlike existing statistical and empirical models, allows estimating the mutual influence of all factors, highlighting the essential properties of incoming information and, ultimately, to improve the accuracy of the forecast without determining all the dependencies between the many factors that determine the ECI process; a method for optimizing the life of a power unit based on an economic criterion that takes into account the diversity of costs and results, the reliability characteristics of the unit's equipment and the cost of repairs and replacements of equipment during operation.

The reliability of scientific provisions is confirmed by a rigorous substantiation of models that describe the processes of operability of the secondary circuit equipment with the correct formulation of the definitions of the limit states of the equipment, methods and provisions, as well as the correspondence of a number of results to operational data. Provisions submitted for defense 1. Significance of factors influencing the aging processes of metals and necessary for individual application of physical and statistical models for assessing and managing the service life of secondary circuit equipment.

2. Physico-statistical models for assessing, predicting and managing the life of equipment in the secondary circuit of NPPs, based on the method of summing damage caused by various aging processes, for carrying out variational calculations and justifying the values ​​of parameters that make it possible to manage the equipment life.

3. Asymptotic methods for solving problems of estimating the resource characteristics of NPP equipment elements based on the Central Limit Theorem (CLT) and their application to damage accumulated in the equipment material under conditions of drop impact erosion of pipeline bends with a two-phase coolant and under stress corrosion cracking of steam generator heat exchange tubes .

4. Method for predicting the resource of tubulars of steam generators of nuclear power plants based on the theory of stochastic filtration.

5. Method for optimizing the volumes and frequency of thickness measurement of NPP equipment elements, taking into account their categorization in terms of FAC speed.

6. Neural network model of the generalized consideration of operating factors for predicting the FAC rate in the elements of equipment of nuclear power plants.

7. Method of optimal management of the service life of a power unit, taking into account the difference in costs and results.

The practical value of the results of the work lies in the fact that, on the basis of the above theoretical provisions and methods, algorithms and engineering methods have been developed that make it possible to justify the values ​​of technological parameters for managing the resource of equipment. The calculations carried out according to the developed methods made it possible to obtain an assessment of the resource indicators of the secondary circuit equipment of NPPs with VVER-1000, VVER-440 and RBMK-1000 reactors at the Kola, Smolensk, Kalinin, Balakovo NPPs and develop recommendations for their management.

The scope of the results is the resource management of SG tubing, heat-exchange condenser tubes, pipeline elements made of pearlitic steels.

Approbation and implementation of results

The work was carried out within the framework of the themes of the Energoatom concern

Diagnostics, equipment resource, steam generators, quality. Feasibility study for the replacement of copper-containing equipment of the KPT for the head unit of VVER-1000 (power unit No. 3 of BlokNPP),

Fundamental problems of decommissioning of nuclear power plants,

Refinement of the "Norms for the permissible thickness of pipeline elements made of carbon steel AS" RD EO 0571-2006 "and" Development of a guidance document for assessing the technical condition of equipment elements and pipelines subject to erosion-corrosion wear ";

A comprehensive program of measures to prevent damage and improve the operational erosion and corrosion resistance of NPP pipelines. No. NPP PRG-550 K07 of Energoatom Concern on the topic "Computational and experimental justification of the volumes and frequency of control of erosion and corrosion wear of pipelines of NPP power units with VVER:1000 reactor plant",

Processing and analysis of the results of thickness measurement of pipeline elements of the 1-3 units of the Smolensk NPP.

The materials of the dissertation were reported and discussed at the following international and all-Russian conferences: 1. System problems of reliability, mathematical modeling and information technologies, Moscow-Sochi, 1997, 1998.

2. NPP safety and personnel training, Obninsk, 1998,1999,2001,

3. 7th International Conference on Nuclear Engineering. Tokyo, Japan, April 1923, 1999 ICONE-1.

4. Control and diagnostics of pipelines, Moscow, 2001.

5. PSAM 7 ESREL 04 International Conference on Probabilistic Safety Assessment and Management, Berlin, 2004.

6. Mathematical ideas P. JI. Chebyshev and their application to contemporary issues natural sciences, Obninsk, 2006.

7. Safety, efficiency and economics of nuclear energy, Moscow,

8. MMR 2007 International Conference on Mathematical Methods in Reliability. Glasgow, Great Britain, 2007.

9. Problems of materials science in the design, manufacture and operation of equipment, St. Petersburg, 2008. Publications. 57 published on the topic of the dissertation scientific works, including 20 articles in scientific and technical journals, 15 articles in collections, 22 in conference proceedings.

The thesis raises methodological issues of predicting the resource of NPP secondary circuit equipment, develops methods based on the physical-statistical approach, and proposes effective computational procedures for calculating resource characteristics.

Major Publications

1. Gulina O. M., Ostreykovskiy V. A. Analytical dependencies for assessing reliability, taking into account the correlation between the load and the bearing capacity of the object// Reliability and quality control. - 1981. - No. 2.-p. 36-41.

2. Gulina O.M., Ostreykovsky V.A., Salnikov H.JI. Generalization of the "parameter-tolerance field" and "load-bearing capacity" models in assessing the reliability of objects//Reliability and quality control.-1982.-№2.-p. 10-14.

3. Gulina O. M., Salnikov N. JI. Building a model for predicting the resource of a pipeline in case of erosion damage. Izvestiya vuzov. Nuclear energy. - 1995. - No. Z.-s. 40-46.

4. Gulina O.M., Salnikov H.JI. Diffusion model for probabilistic forecasting of the resource of nuclear power equipment//Izvestiya vuzov. Nuclear energy. - 1995. - No. 1. - p. 48-51.

5. Gulina O. M., Salnikov N. JI. Model for estimating the resource of SG tubes under conditions of corrosion cracking// Izvestiya vuzov. Nuclear energy. - 1996. - No. 1. - p. 16-19.

6. Egishyants S. A., Gulina O. M., Konovalov E. N. Estimation of resource distribution in case of damage summation. Izvestiya vuzov. Nuclear energy. 1997.-No. 1.- p.18-21.

7. Gulina O.M., Salnikov H.JI. Probabilistic forecasting of the resource of pipelines and pressure vessels AS // Izvestiya vuzov. Nuclear energy. -1998. -No. 1.-C.4-11.

8. Filimonov E.V., Gulina O.M. A generalized integral model for predicting the reliability of NPP pipelines under fatigue loading. Izvestiya vuzov. Nuclear energy. - 1998. - No. Z.-s.Z-l 1.

9. Gulina O.M. Estimation and forecasting of NPP equipment resource. / Scientific research in the field of nuclear energy in technical universities Russia: collection of scientific papers - M .: MPEI, 1999. - S. 201-204.

Yu.Gulina O.M., Salnikov H.JI. Calculation of resource characteristics of equipment under conditions of non-linear effects of degradation processes//Izvestiya vuzov. Nuclear energy. -1999. -#4. -p.11-15.

11. V. A. Andreev, O. M. Gulna. Quick method forecasting the growth of cracks in large-diameter pipelines//Izvestiya vuzov. Nuclear Energy. - 2000. - No. 3. - p. 14-18.

12. Gulina O.M., Zhiganshin A.A., Chepurko V.A. Development of a criterion for optimizing the service life of a power unit // Izvestiya vuzov. Nuclear energy. -2001. -#2. -p.10-14.

13. Gulina O.M., Zhiganshin A.A., Korniets* T.P. Multicriteria problem of optimizing the service life of an ACS power unit/Izvestiya vuzov. Nuclear energy. - 2002.-№4.-p. 12-15.

14. Gulina O.M., Zhiganshin A.A., Mikhaltsov A.V., Tsykunova S.Yu. The problem of assessing the service life of NPP equipment under aging conditions // Nuclear measurement and information technologies. - 2004. - No. 1. - p.62-66.

15. Gulina O.M., Kornienko K.A., Pavlova M.N. Analysis of contamination of the SG tubular and assessment of the interwash period by diffusion processes // Izvestiya vuzov. Nuclear energy. -2006. -№1.-s. 12-18.

16. Gulina O.M., Kornienko K.A., Polityukov V.P., Frolov S.A. Application of the stochastic Kalman filtering method for predicting the resource characteristics of a nuclear power plant steam generator// Atomic Energy. - 2006.-t.101 (4).- p.313-316.

17. Gulina O.M., Salnikov H.JI. Methods for predicting the resource of heat exchange equipment AS// Izvestiya vuzov. Nuclear Energy. - 2007. - No. 3, issue 1. - p. 23-29.

18. Baranenko V.I., Gulina O.M., Dokukin D.A. Methodological basis for predicting erosion-corrosion wear of NPP equipment using neural network modeling // Izvestiya vuzov. Nuclear Energy. - 2008. - No. 1. - p.Z-8.

19. Gulina O.M., Pavlova M.N., Polityukov V.P., Salnikov H.JI. Optimal control of the resource of the NPP steam generator// Izvestiya vuzov. Nuclear Energy. - 2008. - No. 4. - With. 25-30.

20. A. V. Igitov, O. M. Gulina, and H. J. Salnikov, Level optimization problem for detecting discord in an observed random process, Izvestiya vuzov. Nuclear Energy, - 2009-№1.- p. 125-129.

21. Baranenko V.I., Yanchenko Yu.A., Gulina O.M., Tarasov A.V., Tarasova O.S. Operational control of pipelines subject to erosive-corrosive wear// Thermal power engineering.-2009.-№5.-p.20-27.

Similar theses in the specialty "Nuclear power plants, including design, operation and decommissioning", 05.14.03 HAC code

• Study of the erosion and corrosion resistance of the elements of the steam-water path of waste heat boilers of combined-cycle plants and the development of methods for improving it 2010, candidate of technical sciences Mikhailov, Anton Valerievich

• Characteristic features of the calculation justification of the strength of structural elements of nuclear reactors at the stage of operation and when creating new facilities 2007, Doctor of Technical Sciences Sergeeva, Lyudmila Vasilievna

• Modernization and reconstruction of steam generator systems at NPPs with VVER to improve reliability 2009, candidate of technical sciences Berezanin, Anatoly Anatolyevich

• Methodology for monitoring the residual life of equipment and pipelines of VVER reactor plants using an automated system 2012, doctor of technical sciences Bogachev, Anatoly Viktorovich

• Automation of simulation of drop impact erosion of wet-steam turbine blades 2002, candidate of technical sciences Dergachev, Konstantin Vladimirovich

Dissertation conclusion on the topic "Nuclear power plants, including design, operation and decommissioning", Gulina, Olga Mikhailovna

6.5 Conclusions on section 6

1. To assess the frequency of control, models for predicting the development of the ECI process are needed. Methods for predicting the intensity of the ECI process can be classified as follows:

Methods using analytical models;

Methods using empirical models;

Methods of forecasting with the help of artificial intelligence.

2. Analytical models based on the theoretical description of physical processes - individual ECI mechanisms - are able to provide only a qualitative analysis due to the fact that the influence on general process wear is determined by many factors: the geometry of the equipment element, chemical composition metal, type of coolant and operating parameters.

3. Statistical models make it possible to evaluate the general state of the system I f or individual groups of pipeline elements on this moment. Statistical models are based on operational control data. Statistical analysis methods are used to quickly respond to the current situation: identifying elements subject to ECI, estimating the maximum and average speed of ECI, etc. - on the basis of which it is possible to estimate the volume and approximate date of the next control.

4. Empirical models are built on the basis of operational control data and laboratory research results: statistical, physicochemical and neural network models. In order to predict the ECI of the equipment of a specific block, it is necessary to calibrate the empirical model using the field control data of this block. The model obtained as a result of calibration cannot be applied to another block without appropriate adaptation.

5. A large number of parameters that determine the intensity of the ECI process affect each other in a complex way. The use of ANN for solving the problem of FEC forecasting makes it possible to evaluate the mutual influence of all factors, highlight the essential properties of the incoming information and, ultimately, improve the accuracy of the forecast without determining all the dependencies between the many factors that determine the FEC process. This makes it possible to substantiate the neural network approach to determining the intensity of the FAC process in the equipment of the NPP condensate-feed duct.

6. An overview of methods for training neural networks is given and an optimal combination of approaches to creating and training an artificial neural network is proposed, problem solving forecasting the FAC intensity in NPP pipelines. To increase the reliability of the forecast, it is necessary to filter the data, which consists in using only information about thinning, since the FCI process is associated with wall thinning, and thickenings are due to the transfer of corrosion products.

7. The study was carried out on the basis of a simplified artificial neural network that solves the problem of predicting the thinning of the wall of the straight section of the pipeline with a single-phase medium of the CPT of NPP with VVER. The simplified network is trained using the elastic backpropagation algorithm. The area of ​​correct forecasting is determined on the time interval up to 4 years.

8. To optimize the solution of the problem of predicting the FAC rate using the NN, an algorithm is proposed that includes

Performing cluster analysis for the analyzed situations in order to divide them into clusters of situations with similar properties, while the accuracy can be improved by taking into account local and unique dependencies and factors for each cluster. I

Construction for each class of the input set of NN trained using the backpropagation algorithm, which will calculate the thinning of the pipeline wall for the predicted period.

9. The proposed algorithm is implemented using a complex of neural networks

Replicative NS;

Self-organizing map of Kohonnen;

NS backpropagation. t

CONCLUSION

The main theoretical and practical results obtained in the work are as follows.

1. Based on the analysis and systematization of operation data, the features of the impact of physical processes on the aging processes of metals of the secondary circuit equipment, the need to develop and apply physical and statistical models for assessing, predicting and managing the service life of NPP equipment is substantiated. The analysis showed the decisive influence of the presence of copper in the circuit on the intensity of the aging processes of the metal of the equipment of the second circuit of the NPP. An individual approach to assessing the current state of equipment and developing predictive models with the maximum use of available information: data on damage and its causes, factors that intensify damage processes, data from periodic monitoring of the technical condition, chemistry parameters, as well as measures that contribute to mitigating operating conditions and reducing intensity of damage processes, - determines the methods for calculating the resource characteristics of equipment.

2. The mutual influence of the equipment of the condensate-feeding and steam paths, united by a water circuit, on the technical condition of each other, especially on the technical condition and efficiency of the SG operation, is shown. The main aging processes typical for the metal of the secondary circuit equipment, as well as factors affecting the service life of condenser tubes, HDPE and HPH, pipelines and heat exchange tubes of SG are considered. Measures are noted to reduce the intensity of damage processes.

3. Optimization of the service life of a power unit is carried out on the basis of an economic criterion that takes into account the diversity of costs and results, the reliability characteristics of the unit's equipment and the cost of repairs and replacements of equipment during operation - net present value (NPV). The criterion for optimizing the service life is the maximum NPV.

The structure of the payment flow is obtained using the developed Markov model of exploitation. The proposed model for calculating the cost of operation takes into account the loss associated with downtime, the cost of electricity produced, the cost of replacements, the cost restoration work, the cost of modernization measures, etc.

4. Methods have been developed and studied for predicting the service life characteristics of equipment based on the accumulation of damage from the action of various aging processes of the material of the equipment of the secondary circuit of NPP, taking into account their probabilistic nature. To assess the performance of equipment, a stochastic measure of damage is introduced based on the accumulation of damage in the material from the action of certain aging processes. The resource is defined as the moment when the random process of damage accumulation exceeds the set level.

5. The probabilistic characteristics of the resource are obtained by the methods of linear and nonlinear summation of damages - for the processes of drop impact erosion in a two-phase flow and stress corrosion cracking of SG heat exchange tubes - at various concentrations of damaging factors and are calculated on the basis of asymptotic approximations of probability theory and mathematical statistics.

6. For the process of drop-impact erosion, which is typical for bends of steam pipelines, blades of steam turbines, inlet sections of PSTE in HPH, etc., the mechanism of droplet impact on hard surface taking into account the distribution of normal velocities, droplet sizes, as well as such parameters as steam humidity, flow rate, impact spot radius, temperature, pressure, liquid and vapor density, sound velocity in liquid, material parameters.

For SG heat exchange tubes, the damage process is based on the process of stress corrosion cracking, the intensity of which significantly depends on the concentrations of corrosion activators, the presence of deposits on the heat exchange surface, and copper concentrations in deposits, which makes it possible to control the aging process of the SG HOT by justifying the values ​​of the corresponding model parameters.

7. An approach is proposed and justified that uses stochastic linear filtering to take into account heterogeneous information about an object when predicting its resource, as well as to take into account measures taken or planned to reduce the intensity of aging processes. The stochastic Kalman filtering method is adapted to predict the resource characteristics of SG heat exchange tubes. Smoothing filter and predictor algorithms have been developed. Additional information is used in the form of periodic inspection data, the location of the tube in the assembly, wall thickness measurement errors, etc. Based on the requirements for the pace of the aging process, it is possible to evaluate the optimal period or the optimal follow-up plan. The principle of the optimal algorithm for managing the HOT SG resource is formulated.

8. A systematic review of models for predicting FEC in equipment elements is given. Procedures have been developed for processing thickness measurement data on NPP secondary circuit equipment elements to optimize the volumes and frequency of control. Based on the analysis of a large amount of monitoring data for NPPs with VVER-1000, RBMK-1000, VVER-440 reactors - KlnNPP, BlkNPP, NVNPP, KolNPP,

SAES - developed methods and algorithms for processing thickness measurement data, requirements for the type and quality of information provided for calculations, introduced the concept of a category to designate a risk group for intense thinning. It is proposed to include in the control plan elements, the residual life of which is approaching the date of the next outage.

9. The use of neural network modeling for solving the problem of predicting the FAC is justified, which makes it possible to evaluate the mutual influence of all influencing factors, to highlight the essential properties of incoming operational information without determining all the dependencies between the many factors that determine the FAC process. On the example of studying a simplified network for predicting the thinning of the wall of the straight section of the pipeline of the main condensate of a NPP with VVER, trained using the elastic backpropagation algorithm, the correctness of the forecast is shown over a time interval of up to 4 years.

10. To optimize the solution of the problem of predicting the ECI speed using a neural network, an algorithm is proposed that includes

Filtering data for training;

- "identifying" the characteristic features of the input set and reducing the number of input factors on its basis;

Performing cluster analysis for analyzed situations;

Building for each class of a neural network trained using the backpropagation algorithm.

The proposed algorithm is implemented using a set of neural networks: replicative NN; self-organizing map of Kohonnen; NS backpropagation.

List of references for dissertation research Doctor of Technical Sciences Gulina, Olga Mikhailovna, 2009

1. RD-EO-0039-95. Normative and methodological requirements for managing the resource characteristics of NPP power unit elements. M., 1997.

2. Data Collection and Record Keeping for the Management of Nuclear Power Plant Aging IAEA. Safety Practice Publications. #50-P-3, Vienna, 1997.

3. Muratov O.E., Tikhonov M.H. NPP decommissioning: problems and solutions (www.proatom.ru)

4. Ageev A.G., Korolkov B.M., Belov V.I., Semyakin A.A., Kornienko K.A., Trunov N.B. Thermochemical tests of the steam generator PGV-1000M with a reconstructed PDL and a modernized water supply system.// Annual report of ENIC VNIIAES, 1999.

5. Baranenko V.I., Gashenko V.A., Trubkina N.E., Bakirov M.B., Yanchenko Yu.A. Operational reliability of heat-exchange tubes of steam generators of NPP power units with VVER // Proceedings of the seminar at the Kalinin NPP, November 16-18, 1999, pp. 133-158.

6. Methodology for the Management of Aging of Nuclear Power Plant Components Important to Safety IAEA. Technical Reports Series, #338. Vienna, 1998.

7. Baranenko V.I., Baklashov C.A. Analysis of operational damages of condensers and heaters low pressure. Preparation of a schedule for the replacement of condensate-feeder equipment. VM.21.02.00.TO. FGUPVNIIAM. M., 2003.

8. Chexal V.K. (Bind), Horowitz J.S. Chexal-Horowitz Flow-Accelerated Corrosion Model-Parameter and Influences. Current perspective of Inter. Pressure vessels and Piping: Codes and Standard. Book no. 409768.-1995.-P. 231-243.

9. Accident at the nuclear power plant "Sarri-2"// Nuclear technology abroad. -1987.- No. 10. -p.43.

10. Secondary Pipe Rupture at Mihama Power Unit 3. Mr. Hajime Ito.// The Kansai Electric Power Co., Inc. Conf. WANO. 2005. 15 p.

11. T. Inagaki. IAEA activities related to aging management and safe long term operation including FAC// Seminar on Erosion-Corrosion and Flow Assisted Corrosion 6-8 November 2007, Obninsk, Russia.

12. Jens Gunnars. Overview of Erosion-Corrosion// Seminar on Erosion-Corrosion and Flow Assisted Corrosion 6-8 November 2007, Obninsk, Russia.

13. John Pietralik. FAC Seminar: Theoretical Backgrounds// Seminar oni

15. Pipe Break causes death at Surry. // Nucl.Eng.Inter., 1987 v.32. p.4.

16. RD EO 0571-2006. Norms of permissible thicknesses of pipeline elements made of carbon steels of nuclear power plants. 44 p.

17. Bakirov M.B., Kleshchuk S.M., Chubarov S.V., Nemytov D.S., Trunov N.B., Lovchev V.N., Gutsev D.F. Development of an atlas of defects in heat exchange tubes of steam generators at NPPs with VVER. October 3-5, 2006 FSUE OKB "GIDROPRESS".

18. Kharitonov Yu.V., Brykov S.I., Trunov N.B. Predicting the accumulation of deposits of corrosion products on the heat exchange surfaces of the steam generator PGV-1000M// Thermal Power Engineering No. 8, 2001, p.20-22.

19. Ensuring safe and reliable operation of steam generators PGV-1000. Ed. Aksenova V.I. / / Materials of the seminar at the Kalinin NPP, November 16-18, 1999, pp. 78-132.

20. Trunov N.B., Loginov S.A., Dragunov Yu.G. Hydrodynamic and thermochemical processes in steam generators of nuclear power plants with VVER. Moscow: Energoatomizdat, 2001. - 316 p.

21. Baranenko V.I., Oleinik C.j\, Budukin S.Yu., Bakirov M.B., Yanchenko Yu.A., Kornienko K.A. Ensuring the operational reliability of steam generators at NPPs with VVER / / Heavy engineering. -2001, No. 8. - p.6-9.2001. - p.71-72.

22. Yovchev M. Corrosion of thermal power and nuclear power equipment. M.: Energoatomizdat, 1988.- 222 p.

23. Analysis of operational data on maintaining the water-chemical regime of the secondary circuit at power units No. 1-4 of the Balakovo NPP in 2005 / / M., VNIIAES, 2006

24. Analysis of operational data on maintaining the water-chemical regime of the secondary circuit at power units No. 1-4 of BlokNPP for the II quarter of 2006. M., VNIIAES, 2006.

25. Norms for calculating the strength of equipment and pipelines of nuclear power plants (PNAE G-7-002-86). -M.: Energoizdat, 1989.

26. Nikitin V.I. Corrosion damage to steam turbine condensers and determination of the residual life of their pipe system.// Thermal Power Engineering. - 2001. - No. 11. With. 41-45.

27. V.I. Baranenko, O.A. Belyakov. Forecasting the service life of heat exchange tubes of condensers of power unit No. 2 of the Kalinin NPP//Scientific and technical report D. No. 2006/4.15.5/16473 p.26. Elektrogorsk, 2006.

28. Research report. Checking the technology of repair and restoration of NPP heat exchange tubes by applying a polymer coating to the inner surface of heat exchange tubes. M. 2003. Approved. Tech. director of NPO "ROKOR" Ph.D. A.B. Ilyin. -22s.

29. Gulina O.M., Semiletkina I.V. Determination of the latent period of erosive destruction // Diagnostics and prediction of reliability, elements of nuclear power plants: collection of scientific papers of the ACS department. - Obninsk: IATE. - 1992. - No. 8. - p. 31-34

30. Gulina O.M. Estimation and forecasting of the resource of NPP equipment// Scientific research in the field of nuclear energy in technical universities of Russia: collection of scientific papers. M.: MPEI, 1999.- p.201-204.

31. Zb. Zazhigaev JI. S., Kishyan AA, Romanikov Yu. I. Methods of planning and processing the results of a physical experiment. M., Atomizdat, 1978.

32. Antonovich A.V., Butovsky JI.C. Influence of damage to the condenser pipe system on the efficiency of turbine installations at thermal power plants and nuclear power plants // Energetika i electrifikatsiya., 2001. No. 7. pp. 29-34.

33. Nigmatulin B., Kozyrev M: Nuclear energy in Russia. Time of missed opportunities.// Atomic strategy. Electronic journal. July 2008 (www.proatom.ru).

34. Cherkasov V. Nuclear Energy in Russia: Status, Problems, Prospects (http://www.wdcb.ru/mining/doklad/doklad.htm").

35. Rassokhin N.G. Steam generating plants of nuclear power plants. M.: Energoatomizdat, 1987. - 384 p.

36. Baranenko V.I., Oleinik S.G., Budukin S.Yu., Bakirov M.B., Yanchenko Yu.A., Kornienko K.A. Ensuring the operational reliability of steam generators at nuclear power plants with VVER // Heavy Engineering.-2001-No. 8.-p.6-9.

37. N. B. Trunov, V. V. Denisov, Yu. G. Dragunov, G. F. Banyuk, and Yu. Operability of heat-exchange tubes of SG NPPs with VVER.// Proceedings of the IAEA regional seminar "Integrity of SG tubes", Udomlya, November 27-30, 2000 - p.12-18.

38. Ivanisov V.F. Problems of VTK at the Kalinin NPP.// Materials of the seminar at the Kalinin NPP, November 16-18, 1999 - pp. 55-57.

39. Gulina O.M. Estimation and forecasting of NPP equipment resource. /Sat. scientific papers "Scientific research in the field of nuclear energy in technical universities of Russia". M. - MPEI Publishing House. - 1999 - p. 201-204.

40. Gulina O.M., Salnikov H.JI. Probabilistic forecasting of the resource of pipelines and pressure vessels AS.// Izvestiya Universities. Nuclear Energy, 1998.-No. 1.-C.4-11.

41. Gulina O.M., Salnikov H.JI. Methods for predicting the resource of heat exchange equipment AS// Izvestiya vuzov. Nuclear Energy. - 2007. - No. 3, issue 1. - p. 23-29.

42. John Petralik. Liquid Impact Erosion and Cavitation Erosion.// Proceeding of FAC-Seminar. Obninsk, Russia „November 6-8, 2007.

43. Baranenko V.I., Oleinik S.G., Merkushev B.H. et al. Operational reliability of structural elements of steam generators at NPPs with VVER. Questions of atomic science and technology. Ser. Ensuring the safety of nuclear power plants. - 2003, issue Z. - p.85-100.

44. Antonov A.V., Ostreikovsky V.A. Estimation of reliability characteristics of elements and systems of nuclear power plants by combined methods. -M.: Energoatomizdat, 1993.-368s.

45. Skripnik V.M., Nazin A.E., Prikhodko Yu.G. Reliability analysis of technical systems based on censored samples. -M.: Radio and communication, 1988: -289s.

46. ​​Severtsev N.A., Yanishevsky I.M. Reliability of a redundant system with a loaded reserve during preventive maintenance of a reserve element. //Reliability and quality control, -M.: Radio and communication, 1995.-S.94-100.

47. Taratunin V.V., Elizarov A.I., .Panfilova S.E. Application of the method of Markov graphs in problems of distribution of requirements5 to reliability. Technical report-M.: VNIIEAS, 1997. -48p.

48. V. V. Taratunin, A. I. Elizarov. Probabilistic methods for managing the reliability of nuclear power plants, power units; systems: and individual equipment at the operation stage - and extension of the designated: service life. Report on NTS.- M.: VNIIAES, 1999. -57s.

49. Taratunin V.V., Elizarov A.I. Probabilistic assessment of the reliability of equipment and: systems! NPP taking into account aging and operating system MRO. Technical report. Rosenergoatom.-M.: VNIIAES, 2000. -100s.

50. RD-EO-0039-95. Normative and methodological requirements ^ to the management of resource characteristics of elements of power units AS.-M., 1997.

51. N. Davidenko, S. Nemytov, K. Kornienko, V. Vasiliev. The Integrity of the Elements of VVER Steam Generators of Concern Rosenergoatom//

52. Proceedings of IAEA Regional Workshop on "Steam Generator Degradation and Inspection", Saint Denis, France, 1999. Vienna: IAEA, 1999.

53. Gulina O.M., Pavlova M.N., Polityukov V.P., Salnikov H.JI. Optimal control of the resource of the NPP steam generator// Izvestiya vuzov. Nuclear Energy. - 2008. - No. 4. ~ p. 25-30.

54. Gulina O.M., Kornienko K.A., Pavlova M.N. Analysis of SG tubular contamination and evaluation of the interwash period by diffusion processes. // Izvestiya Universities. Nuclear Energy, 2006.- No. 1.- p. 12-18.

55. Gulina O. M., Ostreykovskiy V. A. Analytical dependencies for assessing reliability, taking into account the correlation between the load and the bearing capacity of the object. // Reliability and quality control. - 1981. -№2.-p. 36-41.

56. Gulina O.M., Ostreykovskiy V.A., Salnikov H.J1. Generalization of the "parameter-tolerance field" and "load-bearing capacity" models in assessing the reliability of objects.//Reliability and quality control.-1982.-№2.-p. 10-14.

57. Igitov A.V., Gulina O.M., Salnikov H.JT. The problem of level optimization for the detection of discord in the observed random process.//Izvestiya vuzov. Nuclear "energy. - 2009 - No. 1. - p. 25-29.

58. Implementation and Review of Nuclear Power Plant Aging Management Program IAEA. Safety Reports Series, #15. Vienna, 1999, p.35.

59. Methodology for the Management of Aging of Nuclear Power Plant Components Important to Safety IAEA. Technical Reports Series, #338. Vienna, 1998.

60. Basic Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3, International Atomic Energy Agency, Vienna, 1988; INSAG-8.

61. Kovalevich O.M. Extending the life of NPP power units.//Atomic energy, vol. 88, issue 1, Jan. 2000.

62. RD-EO-0039-95. Normative and methodological requirements for managing the resource characteristics of NPP power unit elements. -M., 1997.

63. RD EO "0096-98. Standard Regulations on the management of the resource characteristics of the elements of AS power units. M., 1997.

64. Tutnov I.A. Management of NPP aging processes// Nuclear technology abroad.-2000.-№4.-p. 10-15.

65. Stepanov I.A. Monitoring of the residual life of NPP equipment in terms of corrosion-mechanical strength of structural materials / / Thermal power engineering. - 1994. No. 5.

66. RD EO-0085-97. Maintenance and repair of systems and equipment of nuclear power plants. Normative duration of repair of EA EB. -M., 1997.

67. RD EO 0077-97. Temporary guidelines on the calculation of the operating capacity of power units of nuclear power plants. M., 1997

68. Sigal E.M. Design ICF as an indicator of the efficiency of using the installed capacity of nuclear power plants / / Atomic energy. -2003.-t.94, issue 2. With. 110-114.

69. IAEA Consultants Report on the Meeting on Nuclear Power Plant Aging and Life Management// IAEA, Vienna, Austria, August, 1989.

70. Akiyama M. Aging Research Program for Plant Life Assessment.// Intern. NPP Aging Symp., August 30 to Sept. 1, 1988, Bethesda, Maryland, USA.

71. Sigal E.M. Ranking of deviations from the normal operation of NPP equipment according to the degree of their influence on the installed capacity utilization factor / / Atomic Energy. - 2002. - v. 92, no. 3.

72. Taratunin V.V., Tyurin M.N., Elizarov A.I. and others. Development of mathematical models for the distribution of requirements for the reliability of components of power units. Computational code preparation. /Report -M.: VNIIAES, 2002.

73. Gulina O.M., Zhiganshin A.A., Korniets T.P. Multicriteria problem of service life optimization.// Izvestiya vuzov. Nuclear Energy. - 2002. - No. 4. - p. 12-15.

76. RF, State Committee RF on construction, architectural and housing policy No. VK 447 of 06/21/1999, M. Economics 2000.

77. Komisarchik T.N., Gribov V.B. Methods of analysis of the comparative economic efficiency of alternative engineering solutions in the design of energy sources.// Thermal power engineering.-2000.*-№8.- p. 58-62.

78. Karkhov A.N. Basics market economy. Fianfond, M., 1994.

79. Kazachkovsky O.D. Fundamentals of the rational theory of value. Moscow: Energoatomizdat, 2000.

80. Kazachkovsky O.D. Calculation of the economic parameters of nuclear power plants / / Atomic energy. - 2001. - vol. 90, issue 4.

81. Karkhov A.N. Economic evaluation of proposals for the construction of nuclear power plants / / Nuclear technology abroad. - 2002. - No. 2. - p. 23-26.

82. Gulina O.M., Zhiganshin A.A., Chepurko V.A. Development of a criterion for optimizing the service life of a power unit.// Izvestiya VUZov. Nuclear Energy. - 2001. - No. 2. - p. 10-14.

83. Gulina O.M., Zhiganshin A.A., Mikhaltsov A.V., Tsykunova S.Yu. The problem of assessing the service life of NPP equipment under aging conditions // Nuclear Technologies and Measurements. - 2004. - No. 1. - p. 62-66.

84. Karkhov A.N. Equilibrium pricing in the energy sector based on discounted value. Preprint No. IBRAE-98-07, M., 1998.

85. O. Gulina, N. Salnikov. Multicriterion Problem of NPP Lifetime Management// PSAM 7 ESREL 04 International Conference on Probabilistic Safety Assessment and Management, June 14-18, 2004, Berlin, Germany.

86. Likhachev Yu.I., Pupko V.Ya. Strength of fuel elements of nuclear reactors / M.: Atomizdat, 1975.

87. Salnikov N.L., Gulina O.M., Kornienko K.A., Frolov S.A. Evaluation of steam generator reliability by damage summation methods (intermediate under contract No. 2004/4.1.1.G.7.7/9224)// Research report. - Obninsk: IATE, 2004. - 71 p.

88. Gulina O.M. Analytical method assessing the reliability of equipment under conditions of damage accumulation.// In Sat. scientific works of the department. ACS "Diagnostics and prediction of the reliability of elements of nuclear power plants". Obninsk. - IATE.-1998. - No. 12. - p.56-59.

89 Gens Gunnars, Inspecta. Overview of Erosion-Corrosion.// Proceeding of FAC-Seminar. Obninsk, Russia „November 6-8, 2007.

90. John Petralik. Liquid Impact Erosion and Cavitation Erosion.// Proceeding of FAC-Seminar. Obninsk, Russia „November 6-8, 2007

91. A. F. Bogachev, Analysis of Heater Damage Data high pressure With. K. D. from the water side // Thermal power engineering.-1991.-No. 7.

92. Shubenko-Shubin JI. A., Shubenko A. JL, Kovalsky A. E. Kinetic model of the process and assessment of the incubation period of destruction of materials exposed to drop flows// Thermal Power Engineering. 1987. - No. 2. - p. 46 - 50.

93. N. Henzel, D.C. Grosby, S.R. Eley. Erosion/Corrosion in Power Plants Single- and Two-Phase Flow Experience, Prediction, NDE Management// p.109-116.

94. Erosion. Iodine ed. K. Pris. M.: Mir, 1982.

95. Kastner W., Hofmann P., Nopper H. Erosion-corrosion on Power Plants// Decision-making Code for Conteracting Material Dragradation VGB Kraftwerktechnik. 1990. - V. 70.- No. 11. - P. 806-815.

96. Gulina O.M., Salnikov H.JI. Building a model for predicting the resource of a pipeline in case of erosion damage//Izvestiya vuzov. Nuclear Energy.-1995.-No. 3.-P.40-46.

97. Kirillov P. JI. Lecture notes on the course "Heat and Mass Transfer (Two-Phase Flows)". Obninsk: IATE, 1991.

98. Chudakov M.V. Methods for ensuring the reliability of NPP pipelines in conditions of drop impact erosion// Diss. for the competition degree Ph.D. St. Petersburg, 2005

99. Kastner V., Knopper H.Yu. Resner R. Protection of pipelines from corrosion erosion// Atomic energy. 1993. - T. 75, issue. 4. -p.286-294.

100. Gulina O.M1., Salnikov H.JI. Estimation of resource characteristics of VVER-440 steam pipelines under conditions of erosive-corrosive wear. Abstracts of reports. Obninsk, October 4-8, 1999

101. Egishyants S. A., Gulina O. M., Konovalov E. N. Estimation of resource distribution in case of damage summation // Izvestiya VUZov. Nuclear Energy.-1997.- No. 1.- p. 18-21.

102. Gosselin S.R., Fleming K.N. Evaluation of pipe failure potential via degradation mechanism assessment.// 5th International Conference on Nuclear Engineering, May 26-30D997, Nice, France.

103. Margolin B.Z., Fedorova B.A., Kostylev V.I. Basic principles for assessing the durability of PGV-1000 collectors and prospects for predicting the life of the collectors of unit No. 1 of the Kalinin NPP / / Materials of the seminar at the Kalinin NPP, November 16-18, 1999. - pp. 61-72.

104. Rassokhin N.G., Gorbatykh V.P., Sereda E.V., Bakanov A.A. Forecasting the resource of thermal power equipment under the conditions of corrosion cracking / / Thermal power engineering. - 1992. - No. 5. pp.53-58.

105. Gulina O. M., Salnikov N. JI. Model for estimating the resource of SG tubes under conditions of corrosion cracking. // News of universities. Nuclear energy. 1996. - No. 1. - pp. 16-19.

106. Karzov G.P., Suvorov S.A., Fedorova V.A., Filipov A.V., Trunov N.B., Brykov S.I., Popadchuk B.C. The main mechanisms of damage to heat exchange pipes at various stages of operation of steam generators of the PGV-1000 type.

107. Local corrosion of metal of thermal power equipment. Ed. Gorbatykh V.P.M.: Energoatomizdat, 1992.

108. Gulina O.M., Salnikov H.JI. Calculation of resource characteristics of equipment under conditions of non-linear effects of degradation processes//Izvestiya vuzov. Nuclear Energy.-1999. -#4. -p.11-15.

109. Baranenko V.I., Malakhov I.V., Sudakov A.V. On the nature of erosion-corrosion wear of pipelines at the first power unit of the South Ukrainian NPP / / Teploenergetika.-1996.-№12.-p.55-60.

110. Gulina O.M., Kornienko K.A., Frolov S.A. Development and research of models for predicting the lifetime of a steam generator.// 9th International Conference "NPP Safety and Training". Tez. report Obninsk, October 24-28, 2005

111. Nadinich B. Establishment of criteria for damping heat exchange pipes in steam generators of nuclear power plants with reactors VVER-440, VVER-1000// Teploenergetika.- 1998.- No. 2. pp. 68-70.

112. Gulina O.M., Kornienko K.A., Polityukov V.P., Frolov S.A. Application of the stochastic Kalman filtering method for predicting the resource characteristics of a nuclear power plant steam generator//Atomic Energy.- 2006.-t.101 (4).- p.313-316.

113. Salnikov H.JI., Gulina O.M., Kornienko K.A., Frolov S.A. and others. Analysis of operational data on the technical condition of the equipment of the KPT (intermediate under contract No. 2004/4.1.1.1.7.7/9224)// Research report. Obninsk: IATE, 2004.- 68 p.

114. Kornienko K. A. Resource management of elements of the condensate-feed path of VVER power units based on the analysis of operational data. Dissertation for the degree of candidate of technical sciences. Obninsk, 2007.

115. Balakrishnan A.V. Kalman filtering theory. M.: Mir, 1988.168 p.

116. A. N. Shiryaev and R. Sh. Liptser, Statistics of Stochastic Processes. -M.: Nauka, 1974. 696 p.

117. Kastner W., Hofinann P., Nopper H. Erosion-corrosion Power Plants. // Decision-making Code for Conteracting Material Dragradation VGB Kraftwerktechnik. 1990. - V. 70, No. 11. - P. 806-815.

118. DASY dokumentiert Wanddichenme|3 Bwerte von Rohrleitungen Siemens AG Unternemensbereich KWU// Hammerbacherstrabe 12-14 Dostfach 32-80, June 1993. D-91056 Eriangen.

119. Case N-480. Examination Requirements for Pipe Wall Thinning Due Single Phase Erosion and Corrosion. Section XI, Division. P.787-795.

120. Certification passport of software EKI-02. Date of registration 17.03.2003, date of issue 19.09.2003

121. Certification passport of software EKI-03. Date of registration 17.03.2003, date of issue 23.06.2003

122. Baranenko V.I. Malakhov I.V. Sudakov A.V. On the nature of erosion-corrosion wear of pipelines at the first power unit of the South Ukrainian NPP / / Teploenergetika. - 1996. No. 12, - P. 55-60.

123. Baranenko V.I. Gashenko V.A. Fields V.I. and others. Analysis of erosion-corrosion wear of pipelines of power unit No. 2 of the Balakovo NPP / / Thermal power engineering. - 1999. - No. 6. - P. 18-22.

124. Baranenko V.I. Oleinik S.G. Yanchenko Yu.A. The use of software tools for the calculation of erosion-corrosion wear of elements of pipeline systems of nuclear power plants//Teploenergetika.-2003.- No. 11.-S. 18-22.

125. Baranenko V.I. Oleinik S.G. Yanchenko Yu.A. etc. Accounting for erosion-corrosion wear during the operation of NPP pipelines.// Thermal power engineering.-2004.- No. 11.- P. 21-24.

126. Baranenko V.I. Oleinik S.G. Filimonov G.N. and others. Ways to improve the reliability of steam generators at power units of nuclear power plants with a VVER reactor.//Teploenergetika.- 2005. No. 12. -S. 23-29.

127. Baranenko V.I., Yanchenko Yu.A. Solving the problem of reducing the erosion-corrosion wear of equipment and pipelines at foreign and domestic nuclear power plants// Thermal power engineering.-2007.-№5.-p.12-19.

128. Typical program of operational control over the condition of the base metal and welded joints of equipment and pipelines of NPP with VVER-1000. ATPE-9-03. 2003.

129. Typical program for monitoring the condition of the base metal and welded joints of equipment and pipelines of NPP with VVER-440 reactor plant during operation. ATPE-2-2005.

130. Typical program of operational control over the condition of the base metal and welded joints of equipment and pipelines of systems important to safety, NPP power units with RBMK-1000. ATPE-10-04. 2004.

131. Typical program for operational control of the state of the base metal and welded joints of equipment and pipelines of the Beloyarsk NPP power unit with the BN-600 reactor plant. ATPE-11-2006.

132. Typical program for operational control of the condition of the base metal and welded joints of equipment and pipelines of systems important to safety, power units of the Bilibino NPP with the EGGT-6 reactor plant. ATPE-20-2005.

133. Managing large amounts of erosion-corrosion NDE data with CEMS. // Nucl. Eng. Inter. May 1990. - P. 50-52.

134. Baranenko V.I., Yanchenko Yu.A., Gulina O.M., Tarasova O.S. Operational control of pipelines subject to erosion-corrosion wear//Heat power engineering.-2009.-№5.-p.20-27.

135. Baranenko V.I., Gulina O.M., Dokukin D.A. Methodological basis for predicting erosion-corrosion wear of NPP equipment using neural network modeling // Izvestiya vuzov. Nuclear Energy. - 2008. - No. 1. - p. 3-8.

136. F. Wasserman. Neurocomputer technology: theory and practice. Translation into Russian by Yu. A. Zuev, V. A. Tochenov, 1992.

137. K. Swingler “Application of Neural Networks. Practical guide". Translation by Yu.P. Masloboeva

138. Gulina O.M., Salnikov H.JI. Building a model for predicting the life of a pipeline in case of damage. Izvestiya vuzov. Nuclear energy. 1995.- No. 3.- p.40-46.

139. Gulina O.M., Filimonov E.V. A generalized integral model for predicting the reliability of NPP pipelines under fatigue loading. Izvestiya vuzov. Nuclear Energy-1998.-No. Z.-s. 3-11.

140. Kozin I.O., Ostrovsky E.I., Salnikov H.JI. Analyzer of the moment of change in the characteristics of random low-frequency processes. Certificate No. 1322330.

141. Tikhonov V.I., Khimenko V.I. Emissions of trajectories of random processes. -M.: Nauka, 1987. 304 p.

142. Gulina O.M., Andreev V.A. A fast method for predicting crack growth in large-diameter pipelines. Izvestiya vuzov. Nuclear energy. 2000. - No. 3. - p. 14-18.

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FEDERAL SERVICE FOR ENVIRONMENTAL, TECHNOLOGICAL
AND NUCLEAR SUPERVISION

ON THE APPROVAL OF FEDERAL NORMS AND RULES
ENERGY "REQUIREMENTS
MANAGEMENT

Article 6 federal law dated November 21, 1995 N 170-FZ "On the use of atomic energy" (Collection of Legislation Russian Federation, 1995, N 48, art. 4552; 1997, N 7, Art. 808; 2001, N 29, Art. 2949; 2002, N 1, art. 2; No. 13, Art. 1180; 2003, N 46, art. 4436; 2004, N 35, Art. 3607; 2006, N 52, Art. 5498; 2007, N 7, Art. 834; No. 49, Art. 6079; 2008, No. 29 Art. 3418; No. 30, Art. 3616; 2009, N 1, art. 17; No. 52, Art. 6450; 2011, N 29, art. 4281; No. 30, Art. 4590, Art. 4596; No. 45, Art. 6333; No. 48, Art. 6732; No. 49, Art. 7025; 2012, N 26, art. 3446; 2013, N 27, art. 3451), subclause 5.2.2.1 of clause 5 of the Regulations on the Federal Environmental Service, approved by Decree of the Government of the Russian Federation of July 30, 2004 N 401 (Collected Legislation of the Russian Federation, 2004, N 32, art. 3348; 2006, N 5, 544; N 23, item 2527; N 52, item 5587; 2008, N 22, item 2581; N 46, item 5337; 2009, N 6, item 738; N 33, item 4081; N 49, item 5976; 2010, N 9, item 960; N 26, item 3350; N 38, item 4835; 2011, N 6, item 888; N 14, item 1935; N 41, item 5750; N 50, item 7385; 2012, N 29, item 4123; N 42, item 5726; 2013, N 12, item 1343; N 45, item 5822; 2014, N 2, item 108 ; N 35, item 4773; 2015, N 2, item 491; N 4, item 661), I order:
Approve the attached federal norms and rules in the field of the use of nuclear power plant equipment and pipelines by nuclear resources. Basic provisions" (NP-096-15).

Supervisor
A.V. ALESHIN

Approved
by order Federal Service
on environmental, technological
and nuclear supervision
dated October 15, 2015 N 410

FEDERAL NORMS AND RULES

TO MANAGEMENT OF THE LIFE OF EQUIPMENT AND PIPELINES
NUCLEAR PLANTS. MAIN PROVISIONS"
(NP-096-15)

I. Purpose and scope

1. These federal norms and rules in the field of the use of atomic energy "Requirements for the management of the resource of equipment and pipelines of nuclear power plants. Basic provisions" (NP-096-15) (hereinafter referred to as the Basic Provisions) were developed in accordance with Article 6 of the Federal Law of November 21 1995 N 170-FZ "On the use of atomic energy" (Collected Legislation of the Russian Federation, 1995, N 48, item 4552; 1997, N 7, item 808; 2001, N 29, item 2949; 2002, N 1 , item 2; N 13, item 1180; 2003, N 46, item 4436; 2004, N 35, item 3607; 2006, N 52, item 5498; 2007, N 7, item 834; N 49 , item 6079; 2008, N 29, item 3418; N 30, item 3616; 2009, N 1, item 17; N 52, item 6450; 2011, N 29, item 4281; N 30, item 4590, item 4596; N 45, item 6333; N 48, item 6732; N 49, item 7025; 2012, N 26, item 3446; 2013, N 27, item 3451), by the Decree of the Government of the Russian Federation of December 1, 1997 N 1511 "On Approval of the Regulations on the Development and Approval of Federal Norms and Rules in the Field of the Use of Atomic Energy" (Sobraniye Zakonodatelstva Rossiyskoy Federatsii, 1997, N 49, art. 5600; 1999, N 27, art. 3380; 2000, No. 28, Art. 2981; 2002, N 4, art. 325; No. 44, Art. 4392; 2003, N 40, Art. 3899; 2005, N 23, Art. 2278; 2006, N 50, art. 5346; 2007, N 14, art. 1692; No. 46, art. 5583; 2008, N 15, art. 1549; 2012, N 51, Art. 7203).
2. These Basic Provisions establish requirements for resource management of equipment and pipelines of nuclear power plants, classified in the designs of nuclear power plant units (hereinafter referred to as NPPs) in accordance with federal norms and rules in the field of the use of atomic energy to elements of 1, 2 and 3 safety classes.
3. These Basic Provisions apply in the design, construction, production, construction (including installation, adjustment, commissioning), operation (including service life extension), reconstruction (modernization), repair and decommissioning of the NPP unit.
4. The terms and definitions used are given in Appendix No. 1 to these Basic Provisions.

II. General provisions

5. These Guidelines apply to resource management of the following NPP equipment and pipelines:
all units of equipment and pipelines, classified in the design of the NPP unit as elements of the 1st safety class;
all pieces of equipment of a single and small-scale production and reference units of NPP pipelines and equipment, classified in the NPP unit design as elements of the 2nd safety class;
individual pieces of equipment and pipelines classified in the design of the NPP unit as elements of safety class 3 in the manner established by the operating organization in agreement with the developers of the designs of reactor plants (hereinafter - RP) and NPP.
6. In the design of the NPP unit for equipment and pipelines, their service life must be justified and assigned.
7. In the design (project) documentation for NPP equipment and pipelines, resource characteristics and resource assessment criteria must be established and justified. For NPP equipment and pipelines designed prior to the entry into force of these Basic Provisions, as well as in cases of termination of the activities of the equipment or pipeline designer, the justification and determination of the life characteristics of NPP equipment and pipelines must be performed by the operating organization.
8. NPP equipment and pipeline resource management should be based on:
a) compliance with the requirements of federal norms and rules in the field of the use of atomic energy, regulatory and guidance documents, instructions for the manufacture, installation, commissioning, operation, maintenance and repair, assessment of the technical condition and residual life of NPP equipment and pipelines;
b) maintaining NPP equipment and pipelines in good (operable) condition by timely detection of damage, implementation of preventive measures (inspections, repairs), replacement of worn-out NPP equipment and pipelines;
c) establishing mechanisms for the formation and development of defects that can lead to destruction or failure of NPP equipment and pipelines;
d) identifying the dominant (determining) mechanisms of aging, degradation and damage to NPP equipment and pipelines;
e) continuous improvement of monitoring of the processes of aging, degradation and damage to NPP equipment and pipelines;
f) the results of monitoring the technical condition and evaluating the depleted and residual life of NPP equipment and pipelines based on the results of monitoring;
g) mitigation (weakening) of the processes of aging, degradation and damage to equipment and pipelines through maintenance, repair, modernization, use of gentle operating modes, replacement (if the resource is exhausted and repair is impossible or inappropriate);
h) development and updating of the NPP equipment and piping resource management program.
9. The operating organization shall ensure the development and coordination with the developers of the RI and NPP designs of the NPP equipment and pipelines resource management program at the stage of their operation and carry out its implementation.
10. The resource management program for equipment and pipelines based on the resource assessment criteria established by design (design) organizations should be focused on preventing damage to NPP equipment and pipelines due to degradation and negative effects of aging of structural materials and the structures themselves during their operation.
11. The NPP equipment and pipeline resource management program should contain:
a) a list of NPP equipment and pipelines, the resource of which is subject to management, and resource characteristics to monitoring, indicating the controlled parameters for each piece of equipment and pipelines;
b) methods for monitoring the processes of damage accumulation in materials and structural elements of NPP equipment and pipelines due to aging, corrosion, fatigue, radiation, temperature, mechanical and other influences affecting the mechanisms of aging, degradation and failures of NPP equipment and pipelines;
c) the procedure for accounting for the technical condition of NPP equipment and pipelines, the actual characteristics of materials, loading parameters and operating conditions, and the procedure for adjusting work programs for operational monitoring of the technical condition of NPP equipment and pipelines;
d) the procedure for the adoption and implementation of measures aimed at eliminating or mitigating damaging factors;
e) the procedure for accounting for the depleted and evaluation of the residual life of NPP equipment and pipelines;
f) the procedure for adjusting the maintenance and repair schedule (hereinafter referred to as MRO) in order to prevent irreversible manifestations of the mechanisms of aging and degradation of NPP equipment and pipelines.
12. Work programs for operational non-destructive testing of the state of the NPP equipment and pipelines metal and regulations for the maintenance and repair of NPP equipment and pipelines must take into account the provisions of the NPP equipment and pipelines resource management program.
13. The operating organization must ensure the collection, processing, analysis, systematization and storage of information throughout the entire service life of equipment and pipelines and maintain a database on damage, their accumulation and development, aging mechanisms, failures and disruptions in operation, as well as on operating modes , including transients and emergencies, in accordance with the NPP equipment and pipeline resource management program.

III. Preparatory measures for management
resource of equipment and pipelines of nuclear power plants
in design and construction

14. At the stage of designing and constructing NPP equipment and pipelines, developers of NPP and RP projects should develop a methodology for managing the resource of NPP equipment and pipelines in the form of a set of organizational and technical measures based on predicting the mechanisms of damage to structural materials of NPP equipment and pipelines, monitoring resource characteristics and identifying the dominant mechanisms of aging and degradation at the operation stage, periodically assessing the actual state of NPP equipment and pipelines and their residual life, corrective measures to eliminate or reduce the mechanisms of aging and degradation, formulating requirements for databases that ensure the implementation of the NPP equipment and pipelines resource management program.
15. Design (design) organizations should provide for measures and means to maintain the values ​​of resource characteristics within the limits that ensure the designated service life of NPP equipment and pipelines.
16. When choosing materials for NPP equipment and pipelines, the mechanisms of damage and degradation of materials (low- and high-cycle fatigue, general and local corrosion, intergranular and transgranular cracking, embrittlement, thermal aging, deformation and radiation damage, erosion, wear, change physical properties), the manifestation of which is possible during the design life of the plant equipment and pipelines, and for non-replaceable plant equipment and pipelines - during the life of the plant.
17. In cases where non-replaceable NPP equipment and pipelines must function during NPP decommissioning, the mechanisms of damage in the period of time, including NPP decommissioning, must be additionally taken into account. The remaining life of such NPP equipment and pipelines should be sufficient to ensure the decommissioning of the NPP.
18. For newly designed NPPs, the design (project) documentation for NPP equipment and pipelines must define a list of non-replaceable NPP equipment and pipelines, methods and tools for monitoring parameters and processes that affect the resource characteristics of NPP equipment and pipelines.
19. For NPP equipment and pipelines of newly designed NPP units, design (project) documentation for NPP equipment and pipelines must contain:
a) a list of design modes, including normal operation modes (start-up, stationary mode, reactor power change, shutdown), abnormal operation modes and design basis accidents;
b) the estimated number of repetitions of all design regimes for the designated service life of NPP equipment and pipelines;
c) operating conditions and loads on NPP equipment and pipelines;
d) a list of potential mechanisms for damage and degradation of NPP equipment and pipeline materials that can affect their performance during operation (low- and high-cycle fatigue, general and local corrosion, intergranular and transgranular cracking, embrittlement under the influence of temperature, neutron or ionizing radiation, thermal aging, creep, deformation damage, erosion, wear, formation and growth of cracks, taking into account the influence of the environment and creep, changes in physical properties);
e) results of NPP equipment and pipelines strength and resource calculations, substantiation of their service life. The resource of non-replaceable NPP equipment and pipelines must be provided for the lifetime of the NPP unit and for the period of decommissioning of the NPP unit.
20. The design (project) documentation for NPP equipment and pipelines shall take into account the accumulated experience in operating NPP units, as well as experience in manufacturing, installation, commissioning, operation and decommissioning of NPP equipment and pipelines, and the results of scientific research.
21. For newly designed NPP units, the design (project) documentation for NPP equipment and pipelines shall provide systems and (or) methods for monitoring the necessary parameters that determine the resource of NPP equipment and pipelines throughout their entire service life, from the following list:
temperature;
heating or cooling rate;
temperature gradients along the wall thickness;
pressure and rate of increase or release of pressure of the coolant or working media;
vibration characteristics;
temperature and humidity in the room where the equipment and (or) pipelines are located;
illumination intensity;
the degree of oxidation of the lubricant;
flow rate of the coolant or working media;
number of loading cycles;
changes in wall thicknesses;
radiation exposure;
the intensity of the electromagnetic field at the locations of equipment and (or) pipelines;
movement of control points of NPP equipment and pipelines during heating or cooling down, as well as under external and (or) internal influences;
characteristics of external influences;
output signals of electronic units.
For NPPs under construction and in operation, the procedure for retrofitting NPP equipment and pipelines with systems and (or) methods for monitoring the necessary parameters from the above list shall be established.
22. The thicknesses of the walls of NPP equipment and pipelines, which are established during the design, must take into account the processes of corrosion, erosion, wear that occur during operation, as well as the results of predicting changes in the mechanical characteristics of materials due to aging by the end of the life of NPP equipment and pipelines.
23. The design (project) documentation for NPP equipment and pipelines shall provide for the possibility of their inspection, maintenance, repair, periodic monitoring and replacement (with the exception of non-replaceable NPP equipment and pipelines) during operation.
24. The design and layout of NPP equipment and pipelines should not interfere with the implementation of control, inspections, tests, sampling in order to confirm the predicted values ​​and rates of changes in resource characteristics associated with the mechanisms of aging and degradation of structural materials during the operation of NPP equipment and pipelines.
25. Design (design) organizations should develop methods for assessing and predicting the residual life of NPP equipment and pipelines. The RI and NPP designs shall provide for methods and technical means operational control and diagnosing the state of NPP equipment and pipelines, maintenance and repair, allowing timely detection of manifestations of the mechanisms of aging and degradation of structural materials during operation.
26. For NPPs being designed and constructed, the life characteristics and methodology for managing the life of NPP equipment and pipelines shall be reflected in the design (project) documentation for NPP equipment and pipelines and safety analysis reports.

IV. Production resource management
equipment and pipelines of nuclear power plants and construction
nuclear power plants

27. During the production, transportation, storage and installation of NPP equipment and pipelines or their constituent parts enterprises - manufacturers of NPP equipment and pipelines and installation organizations must immediately provide the operating organization with data that can affect the service life of NPP equipment and pipelines, including:
on the presence or absence of deviations from the design (project) documentation for NPP equipment and pipelines and their manufacturing technology (if there are deviations, detailed description deviations), repairs, heat treatments, additional tests;
about methods of protection of NPP equipment and pipelines from corrosion during storage, operation and scheduled preventive maintenance.
28. Passports of NPP equipment and pipelines should contain their designated service life and resource characteristics.
29. Prior to putting the NPP unit into operation, the operating organization, with the involvement of NPP and RP project developers, must:
a) develop a NPP equipment and piping resource management program, which should reflect the NPP equipment and piping resource management methodology, taking into account the scheme given in Appendix No. 2 to these Basic Provisions.
b) prepare software for maintaining a database on NPP equipment and pipelines, which allows, at any stage of the life cycle of a NPP unit, to collect, store and compare the initial and actual values ​​of their resource characteristics, record and analyze information about equipment operating conditions that can affect the resource and NPP pipelines;
c) develop a procedure for collecting and storing data necessary for the implementation of the NPP equipment and pipelines life management program and assessment of their residual life, with special attention to be paid to the most loaded welded joints, areas with the highest stresses (including local areas with a high concentration of stresses), places with the highest temperature and maximum temperature gradients (differences), places subject to the greatest radiation embrittlement, as well as areas subject to vibration, corrosive and erosive wear.

V. Resource management of equipment and pipelines of nuclear
plants at the stage of operation of a nuclear power plant

30. The resource of equipment and pipelines must be confirmed, maintained and, if technically possible, restored at the expense of maintenance and repair with a frequency specified in the program for managing the resource of equipment and pipelines of the NPP.
31. The results of monitoring of the technical condition of the NPP equipment and pipelines carried out at the NPP unit shall be taken into account when assessing the depleted and forecasting residual life of the NPP equipment and pipelines using data on the actual operating conditions of the NPP equipment and pipelines in accordance with the NPP equipment and pipelines resource management program. In cases where the residual life of equipment and pipelines is exhausted or not determined, the operation of such equipment and pipelines of the NPP is not allowed.
32. If any damage or deviations from the requirements of the design (project) documentation are detected during operation and during periodic monitoring of the technical condition of NPP equipment and pipelines, information about them must be entered by the operating organization into the database for its subsequent use in managing the resource of equipment and pipelines NPPs, assessment of their residual life, as well as in probabilistic safety assessment and periodic assessment of NPP operation safety.
33. In order to predict the degradation of NPP equipment and pipelines and their materials, as well as to develop timely corrective or mitigating mechanisms for degradation, monitoring and forecasting of trends in degradation mechanisms should be carried out. Methods for detecting the manifestations of degradation mechanisms, the frequency of their control, as well as the analysis of control results should ensure the identification of degradation mechanisms at an early stage of their manifestation and the adoption of timely measures before the occurrence of irreversible consequences due to their development.
34. In case of detection of factors not provided for in the RI and NPP designs that can adversely affect the mechanisms of degradation of NPP equipment and pipelines and their materials and lead to accelerated depletion of the residual life of NPP equipment and pipelines, the operating organization must provide all necessary information organizations - developers of RI and NPP projects to take these factors into account in RI and NPP projects. After receiving this information, the organizations - developers of RI and NPP designs should assess the impact of factors not provided for in the design on the service life of NPP equipment and pipelines, propose measures to eliminate or reduce the impact of such factors. These measures must be taken into account in the NPP equipment and pipeline resource management program.
35. The need for corrective measures in the operation of NPP equipment and pipelines must be established by the operating organization based on an analysis of their degradation rates.
36. The designated service life of NPP equipment and pipelines shall be reduced if factors not provided for in the RI or NPP designs are detected that adversely affect the mechanisms of aging and degradation and lead to an accelerated depletion of the residual life of NPP equipment and pipelines that is irreversible and uncontrollable by corrective measures.
37. The service life of NPP equipment and pipelines may be extended if their resource is not exhausted and the residual life of the NPP equipment and pipelines allows to continue the safe operation of the NPP unit.

VI. Resource Management at the Extended Life Stage
equipment and pipelines of nuclear power plants

38. Extension of the service life of NPP equipment and pipelines beyond the designated one is allowed only if there is a justification prepared by the operating organization based on the results of the implementation of the program for managing the life of NPP equipment and pipelines and agreed by the organizations - developers of NPP and RI projects within their design boundaries.
39. If there are positive results of justifying the possibility of extending the service life of NPP equipment and pipelines, the operating organization must issue a decision to extend their service life and make the necessary changes to the NPP equipment and pipelines resource management program. For NPP equipment and pipelines, the life of which has been exhausted by more than 80%, an increase in the scope of technical condition monitoring and (or) a reduction in the intervals between periodic assessments of the residual life of NPP equipment and pipelines should be provided.
40. The results of periodic assessments of the residual life of NPP equipment and pipelines at the stage of extended service life should be taken into account in safety analysis reports.
41. When extending the life of the NPP unit, the extension of the service life of non-replaceable equipment and pipelines of the NPP should be carried out as part of the work to extend the life of the NPP unit in accordance with the requirements of regulatory documents governing the procedures for extending the life of the NPP unit, taking into account the data on the implementation of the resource management program NPP equipment and pipelines.

VII. Equipment resource management
and pipelines of nuclear power plants during the decommissioning of a nuclear power unit
stations out of service

42. Prior to NPP unit decommissioning, the operating organization shall develop a separate NPP equipment and piping resource management program, which includes only the equipment and pipelines of the NPP equipment and pipelines used during decommissioning of the NPP unit.
43. The NPP equipment and pipeline resource management program at the NPP unit decommissioning stage shall be coordinated with the NPP unit decommissioning stages and shall take into account the order and sequence of dismantling and disposal of the NPP equipment and pipelines.
44. The sequence of dismantling of NPP equipment and pipelines should be based on the NPP unit decommissioning program.
45. The residual life of non-replaceable NPP equipment and pipelines used when decommissioning the NPP unit must be ensured until the complete decommissioning of the NPP unit.
46. ​​The resource management of non-replaceable equipment and pipelines used during decommissioning of the NPP unit must continue until the completion of their dismantling in accordance with the stages and sequence provided for by the decommissioning program of the NPP unit.

Appendix No. 1

in the field of nuclear
energy "Requirements for management
resource of equipment and pipelines


environmental services,
technological and nuclear supervision
dated October 15, 2015 N 410

TERMS AND DEFINITIONS

The following terms and definitions are used in these Guidelines:
1. Depleted resource - change in the values ​​of resource characteristics of equipment and pipelines from the beginning of their operation to the current moment of operation (or control of their technical condition).
2. Degradation - negative structural changes in structural materials or the structures of equipment and pipelines themselves under the influence of mechanical loads, temperature and / or the environment.
3. Mechanisms of aging - processes leading to irreversible changes in the properties of structural materials during operation.
4. Assigned service life - the calendar service life of equipment and pipelines established and justified in the NPP and RI designs (including periods of maintenance and repair).
5. Non-replaceable equipment and pipelines - equipment and pipelines, the replacement of which during operation is technically impossible or not economically feasible.
6. Equipment - elements of the NPP unit, classified by the developers of NPP and RP projects in accordance with federal norms and rules in the field of atomic energy use to safety classes 1, 2 and 3 according to the degree of influence on safety.
7. Residual resource - the difference between the installed and depleted resource.
8. Extended service life - calendar duration (period) of operation of equipment and pipelines in excess of the designated service life.
9. Damage - a consequence of mechanical, physical or chemical impact on the structure, leading to a decrease in its resource.
10. Resource - the total operating time of equipment and pipelines from the beginning of their operation to the point in time at which an irreversible violation of the strength or performance conditions established by regulatory documents occurs.
11. Resource characteristics - quantitative values ​​of the parameters that determine the resource of equipment and pipelines.
12. Reference piece of equipment - one or more pieces of typical equipment selected for the implementation of resource management measures according to the criteria of the highest load and / or the most severe operating conditions.
13. Aging - the process of accumulation over time of changes in the mechanical and / or physical characteristics of the structural materials of equipment and pipelines.
14. Resource management - a set of organizational and technical measures aimed at maintaining or reducing the rate of depletion of the resource of equipment and pipelines during their operation.

Appendix No. 2
to federal rules and regulations
in the field of nuclear
energy "Requirements for management
resource of equipment and pipelines
nuclear power plants. Fundamentals",
approved by order of the Federal
environmental services,
technological and nuclear supervision
dated October 15, 2015 N 410

SCHEME
LIFE MANAGEMENT OF EQUIPMENT AND PIPELINES OF NUCLEAR
STATIONS IN OPERATION

Planning
┌────────────────────────────────────┐
│2. Execution and optimization │
│ resource management work │
├────────────────────────────────────┤
│Preparation, coordination, technical│
│maintenance and adjustment │
│resource management activities:│
Improvement │- regulatory requirements │
programs on │documentation and safety criteria│
management │- measures envisaged │ Mitigation
resource │ normative documentation │ expected
│- description of mechanisms of coordination │ degradation
┌───────────\ │- increase in efficiency │ ┌─────────────┐
│ ┌─────────/ │ resource management based on │ └─────────┐ │
│ │ │ self-assessment and expertise │ │ │
│ │ └────────────────────────────────────┘ │ │
│ │ / \ │ │
└─┘ │ │ \ /
Actions \ / Execution
┌──────────────────────────┐ ┌─────────────────────────────────────┐ ┌──────────────────────┐
│5. Technical │ │1. The study of aging processes and │ │3. Operation │
│ maintenance │ │ degradation │ │ equipment │
├───────────────────────────┤ ─────────────────┤ │(pipelines) │
│Effect management │ │Information underlying │ ├───────────────────────────────────────────────────────────────
│degradation: │ │resource management: │ │Mechanism management│
│- precautionary │ │- materials, their properties and methods │ │ degradation: │
│maintenance │ │manufacturing │ │- operation in │
│- corrective │/───\│- loads and operating conditions │/────\│according to the set- │
│maintenance │\───/│- mechanisms and degradation zones │\────/│updated procedures│
│- assortment optimization│ │- consequences of degradation and failures │ │and documentation │
│spare parts │ │- research results │ │- control of water chemistry- │
│- replacement │ │- operating experience │ │Cal mode │
│- maintaining the history of maintenance and repair │ │- prehistory of control and technical │ │- environmental control │
│ │ │service │ │environment │
│ │ │- mitigation/deceleration methods │ │- recording parameters and │
│ │ │- Current state, sensors │ │operating history │
└──────────────────────────┘ └─────────────────────────────────────┘ └──────────────────────┘
/ \ / \ ┌─┐
│ │ │ │ │ │
│ │ \ / │ │
│ │ Check │ │
│ │ ┌─────────────────────────────────────────┐ │ │
│ └────────┐│4. Survey, monitoring and evaluation │ /───┘ │ Verification
└──────────┘│technical condition │ \──────┘ implementation
├──────────────────────────────────────────┤ mechanisms
Mitigation of effects │Detection and evaluation of degradation effects:│ degradation
degradation │- test and checks │
│- pre-operational and operational │
│control │
│- observation │
│- leak detection, monitoring │
│vibrations│
│- performance assessment │
│- database support │
└─────────────────────────────────────────┘

As a manuscript

UDC 621.039.586

GULINA OLGA MIKHAILOVNA

PHYSICAL AND STATISTICAL MODELS OF LIFE MANAGEMENT OF EQUIPMENT OF THE SECOND CIRCUIT OF NUCLEAR POWER PLANTS

Specialty 05.14.03 - nuclear power plants, including design, operation and decommissioning

A V T O R E F E R A T

dissertations for a degree

doctor of technical sciences

Obninsk - 2009

The work was done in the State educational institution higher professional education "Obninsk State Technical University of Nuclear Energy"

Official opponents Doctor of Technical Sciences Davidenko

Nikolai Nikiforovich

Doctor of Technical Sciences Gorbatykh

Valery Pavlovich

doctor of technical sciences Gashenko

Vladimir Alexandrovich

Lead organization

The defense will take place 23 » _ 09_ 2009 V _ 14 _hour_ 00 __min. at a meeting of the dissertation council D 212.176.01 at the Obninsk State Technical University of Atomic Energy Kaluga region, Obninsk, Studgorodok, 1, IATE, meeting room of the Academic Council.

The dissertation can be found in the library of the Obninsk State Technical University of Atomic Energy.

Scientific Secretary

dissertation council D 212.176.01

d.f.-m. n., professor

general description of work

The dissertation work is aimed at solving the problem of effective management of the service life of the secondary circuit equipment of nuclear power plants.

The relevance of the work. The safety of nuclear power plants is largely determined by the reliable operation of the steam generation system and the external cooling system, consisting of steam turbine condensers and a regeneration system.

The safe operation of NPP power units and measures to extend the service life are impossible without careful observance of the rules and regulations for operation and maintenance, analysis of the effectiveness of certain control actions, development of methods for probabilistic forecasting of equipment life characteristics, as well as the introduction of modern procedures for processing monitoring data. Reviews, papers, etc. are devoted to these issues.

But in addition to the safety condition, the operation of the power unit is also subject to the condition of economic efficiency of operation. These problems are considered and developed in works, etc. The efficiency of electricity production largely depends on the downtime of the unit associated with preventive maintenance or elimination of the causes of NPP equipment failures. The classification of equipment important from the point of view of the impact on safety, made in different countries developing nuclear power, outlined the main types of equipment that should be considered when deciding to extend the service life. These issues are substantively considered in the IAEA documents, in papers, etc. The influence of the selected equipment on the installed capacity utilization factor (ICUF) of the power unit (PU) is due to downtime due to the unreliability of this equipment. One of the main tasks in this regard is to predict the reliability characteristics of equipment and evaluate the effectiveness of control measures based on models of aging processes that limit its resource. In a large number of works devoted to the development of theoretical models of these processes, the presented models are quite complex and contain a large amount of specific data, which makes it difficult to use such models in resource prediction. As a rule, statistical information about failures and operating time is used for forecasting.

Currently, the problem of optimizing the service life of a power unit is topical, taking into account the effects of equipment metal aging and the cost of modernization measures. A feature of the task of optimizing the service life of an EB is that it is a task of individual forecasting, therefore, it is required to organize the collection and processing of initial information, justify the choice of an economic criterion, and formulate an optimization principle taking into account the economic situation during the operation of a particular EB.

The secondary circuit equipment plays a special role in this regard, since it is subject to different aging processes, operates in different conditions, the assigned resource, as a rule, is commensurate with the resource of the block, and replacement has a rather high cost.

The aging processes of secondary circuit equipment materials, as well as NPP equipment in general, are objective, and for timely effective resource management, observations and analysis of the technical condition of equipment during operation and widespread use of diagnostic and non-destructive testing programs are required. Observation data must be processed in a timely and high-quality manner and used in predicting the resource characteristics of equipment.

Therefore, the need to develop approaches, methods and algorithms for setting and solving the problem of optimizing the EB service life, developing methods for predicting the resource, taking into account various factors, the nature of the aging process and its probabilistic nature, as well as using computational procedures that allow obtaining effective estimates, determines the relevance of the dissertation work.

Object of study - NPP secondary circuit equipment.

Subject research is the evaluation of the resource characteristics of the equipment of the second circuit of the NPP.

The purpose and objectives of the study - development of theoretical foundations and applied models for assessing, predicting and managing the service life of NPP secondary circuit equipment based on statistical processing of data on operation and taking into account the mechanisms of aging processes.

To achieve this goal, the following tasks are solved.

1. Analysis and systematization of operation data from the point of view of the impact of physical processes on the aging processes of secondary circuit equipment materials and justification for the use of physical and statistical models for individual assessment, prediction and management of the service life of NPP secondary circuit equipment.

2. Development of methods for predicting the resource characteristics of secondary circuit equipment under conditions of damage accumulation from the action of various material aging processes, taking into account their probabilistic nature.

3. Development of methods and algorithms for optimizing the service life of a power unit based on an economic criterion that takes into account the diversity of costs and results, the reliability characteristics of the unit's equipment and the cost of repairs and replacements of equipment during operation.

4. Development of methods for solving the problem of reaching the limit state by elements of NPP equipment.

5. Optimization of volumes and frequency of monitoring the technical condition of NPP secondary circuit equipment subject to erosion-corrosion wear.

6. Development of a method for predicting the intensity of the FCI process of NPP equipment elements made of pearlitic steels based on the theory of neural networks.

Research methods. The work is based on the use and development of methods for the safe operation of nuclear power plants, reliability theory, probability theory and mathematical statistics, using which the following were carried out:

· analysis of operating factors limiting the service life of NPP equipment;

· analysis of statistical data on the operability of NPP equipment;

Scientific novelty work is that, in contrast to existing approaches to determining the service life of a power unit, the proposed concept uses the formulation of the problem taking into account the effects of aging of NPP equipment, and also that methods have been developed for predicting the resource characteristics of equipment using models of physical aging processes, more the amount of information on the operating parameters and measures taken to manage the service life of the secondary circuit equipment of nuclear power plants. When developing methods for assessing and predicting resource characteristics, a number of new theoretical results were obtained:

The significance of the factors that determine the intensity of aging processes in the material, which is necessary to manage the resource of specific NPP equipment;

- a probabilistic model for predicting the resource of the heat exchange tubes of the steam generator based on the methods of linear and nonlinear summation of damages, taking into account the operating parameters and the type of the main aging process;

Asymptotic methods for solving the problem of reaching the limit state by equipment elements: in the drop impact erosion model under conditions of two-phase coolant flows, in damage summation methods in the problem of estimating the SG TOT resource;

A method for predicting the resource of a steam generator tube based on linear stochastic Kalman filtering, which allows taking into account a large amount of operational data, control data and research results based on mathematical models of damage processes and ongoing preventive measures, which, in contrast to known methods, leads to an increase in the reliability of the forecast and the possibility to qualitatively manage the tubular resource on the basis of the formulated principle of optimal control;

A method for optimizing the volumes and frequency of control of the thickness of NPP equipment elements subject to erosion-corrosion wear, based on the proposed method for processing control data and determining the elements belonging to the EQI risk group, calculating the allowable wall thicknesses and ranking the elements according to the degree of wear and EQI rate, based on the first analysis of a large number of measurements at the Kola, Kalinin, Balakovo, Novovoronezh, Smolensk NPPs;

A neural network model for assessing and predicting the performance of equipment elements subject to erosion-corrosion wear, based on the observed parameters that determine the intensity of the ECI process, and control data, which, unlike existing statistical and empirical models, allows estimating the mutual influence of all factors, highlighting the essential properties of incoming information and, ultimately, to improve the accuracy of the forecast without determining all the dependencies between the many factors that determine the ECI process;

A method for optimizing the life of a power unit based on an economic criterion that takes into account the diversity of costs and results, the reliability characteristics of the unit's equipment and the cost of repairs and replacements of equipment during operation.

Reliability of scientific statements is confirmed by a rigorous substantiation of models that describe the operability processes of the secondary circuit equipment with the correct formulation of the definitions of the limit states of the equipment, methods and provisions, as well as the correspondence of a number of results to operational data.

Regulations put up for defense

1. Significance of the factors influencing the aging processes of metals and the physical-statistical models necessary for the individual application of assessing and managing the service life of secondary circuit equipment.

2. Physico-statistical models for assessing, predicting and managing the life of equipment in the secondary circuit of NPPs, based on the method of summing damage caused by various aging processes, for carrying out variational calculations and justifying the values ​​of parameters that make it possible to manage the equipment life.

3. Asymptotic methods for solving problems of estimating the resource characteristics of NPP equipment elements based on the Central Limit Theorem (CLT) and their application to damage accumulated in the equipment material under conditions of drop impact erosion of pipeline bends with a two-phase coolant and under stress corrosion cracking of steam generator heat exchange tubes .

4. Method for predicting the resource of tubulars of steam generators of nuclear power plants based on the theory of stochastic filtration.

5. Method for optimizing the volumes and frequency of thickness measurement of NPP equipment elements, taking into account their categorization in terms of FAC speed.

6. Neural network model of the generalized consideration of operating factors for predicting the FAC rate in the elements of equipment of nuclear power plants.

7. The method of optimal control of the service life of a power unit, taking into account the difference in costs and results.

Practical value of the results work lies in the fact that on the basis of the above theoretical provisions and methods, algorithms and engineering methods have been developed that allow justifying the values ​​of technological parameters for managing the resource of equipment. The calculations carried out according to the developed methods made it possible to obtain an assessment of the resource indicators of the secondary circuit equipment of NPPs with VVER-1000, VVER-440 and RBMK-1000 reactors at the Kola, Smolensk, Kalinin, Balakovo NPPs and develop recommendations for their management.

Scope of the results - resource management of SG tubing, heat exchange condenser tubes, pipeline elements made of pearlitic steels.

Approbation and implementation of results

The work was carried out within the framework of the themes of the Energoatom concern

Diagnostics, equipment resource, steam generators, quality. Feasibility study for the replacement of copper-containing equipment of the KPT for the head unit of VVER-1000 (power unit No. 3 of BlokNPP),

Fundamental problems of decommissioning of nuclear power plants,

Refinement of the "Norms for the permissible thickness of pipeline elements made of carbon steel AS" RD EO "and" Development of a guidance document for assessing the technical condition of equipment elements and pipelines subject to erosion-corrosion wear ";

A comprehensive program of measures to prevent damage and improve the operational erosion and corrosion resistance of NPP pipelines. No. NPP PRG-550 KO7 of Energoatom Concern on the topic "Computational and experimental substantiation of the volumes and frequency of control of erosion and corrosion wear of pipelines of NPP power units with VVER-1000 reactor plant",

Processing and analysis of the results of thickness measurement of pipeline elements of the 1-3 units of the Smolensk NPP.

The dissertation materials were reported and discussed at the following international and all-Russian conferences:

1. System problems of reliability, mathematical modeling and information technologies, Moscow-Sochi, 1997, 1998.

2. NPP safety and personnel training, Obninsk, 1998, 1999, 2001, 2003, 2005, 2007

3. 7th International Conference on Nuclear Engineering. Tokyo, Japan, April 19-23, 1999 ICONE-7.

4. Control and diagnostics of pipelines, Moscow, 2001.

5. PSAM 7 ESREL 04 International Conference on Probabilistic Safety Assessment and Management, Berlin, 2004.

6. Mathematical ideas and their application to modern problems of natural science, Obninsk, 2006.

7. Safety, efficiency and economics of nuclear energy, Moscow, 2004, 2006.

8. MMR 2007 International Conference on Mathematical Methods in Reliability. Glasgow, Great Britain, 2007.

9. Problems of materials science in the design, manufacture and operation of equipment, St. Petersburg, 2008.

Publications. 57 scientific papers have been published on the topic of the dissertation, including 20 articles in scientific and technical journals, 15 articles in collections, 22 in conference proceedings.

The thesis raises methodological issues of predicting the resource of NPP secondary circuit equipment, develops methods based on the physical-statistical approach, and proposes effective computational procedures for calculating resource characteristics.

The dissertation consists of 6 sections, introduction, conclusion, list of references of 169 titles, five appendices - 344 pages in total.

IN first chapter the main problems associated with the unreliability of the secondary circuit equipment are considered: the main mechanisms of damage, the criteria for the limit state, economic problems associated with the replacement of equipment. The analysis of the factors limiting the resource of the equipment (indicators of the water-chemical regime (WCM) and their dynamics, the dependence of the resource on the factors of operation) was carried out, the individual nature of the equipment aging within the same unit and at different NPPs was shown, the technical condition of the BlakNPP capacitor was assessed by the analog method. The resource assessment was made according to the criterion of permissible jamming of 10% of condenser tubes with a "lack of metal" of more than 70% (Fig. 1). On the ordinate axis - the proportion of rejected pipes from the total number in%, on the abscissa - the time of the maintenance work minus 1990. The estimation error is taken into account using the confidence interval , where is the value of the confidence interval (CI), β is the confidence probability (β = 0.95 ), n- number of measurements (sample size), - Student's distribution quantile, Dispersion" href="/text/category/dispersiya/" rel="bookmark">dispersion , . At n=3 when quantile t 3, 0.95 equals 2.35 , A https://pandia.ru/text/78/197/images/image002_31.gif" width="29 height=29" height="29">=0.97.

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Crossing the upper limit of CI with an acceptable level (in this case 10%) gives the lower bound of the resource. In this case, the lower limit of the resource differs from the average by about half a year.

Regularities and features of aging of heat exchange tubes (HET) of SG at different units and different NPPs are noted. The regularities that appear on the HOT SG during operation include the aging of the material under the influence of damaging factors, which manifests itself in the form of defect growth, mainly under deposits of corrosion products. The main mechanisms of damage to SG heat exchange tubes are pitting, pitting and stress corrosion cracking. These degradation mechanisms account for 68-85% of TOT damage from the total number of damages. The origin and development of HOT damage is facilitated by the presence of deposits of corrosion products on the outer surface of the HOT. Surface contamination also impairs heat transfer between the primary and secondary circuits, which reduces steam production. The main dependencies were found between the number of silted HOTs and the amount of iron and copper in the sediments, the average specific surface contamination, and the location of HOTs in the assembly. Appropriate approximations and estimates are given. For example, the dependence of the number of silted HOTs (THOTs) on the average specific pollution is quite well described by a linear function (Fig. 2).

A)

Figure 2. Empirical dependence of the number of plugged HOTs on the average specific contamination for 1PG-1 (a) and 1PG-3 (b) of KlnNPP.

Individual are: the intensity of aging, the distribution of the number of muffled HOT along the height of the tube sheet, carried out preventive actions and their frequency, the technical condition of the SPT equipment and their materials, water chemistry, kill criteria, etc..gif" width="129 height=38" height="38">.

Knowing the permissible level of HOT contamination for a given SG (criterion of the limiting state), it is possible to estimate the time until the first exit of the process of pollution growth beyond the permissible limit. However, the average trend forecast is not a conservative estimate. Therefore, it is necessary to estimate the error of the obtained estimates by constructing a confidence interval.

https://pandia.ru/text/78/197/images/image019_16.gif" width="337" height="232 src=">

Figure 3. Approximation of pollution for 1SG-3 KlnNPP

Calculation with different initial values ​​of the residual average specific contamination gives the following values ​​of the lower limit of the 95% CI for the time of going beyond the permissible limits indicated in Table. 1.

Table 1

Values ​​of the interflushing period at various values ​​of residual contamination for 1PG-3

Initial value, g/m2	Permissible level d, g/m2	Flushing period, thousand hours

An analysis of the statistical and physico-statistical approaches to assessing the residual life of equipment is given, an overview of models for calculating the resource characteristics of elements is given, and an analysis of efficiency is carried out. various events resource management, which determines the significance of operating factors.

In second chapter the main problems associated with optimizing the service life of the NPP EBs are considered: the choice of an economic criterion, the ranking of equipment, the development of a payment flow model, etc.; a solution to the problem of detecting a discord in an observed random process associated with the onset of aging is given.

The criteria for making the decision "life extension - decommissioning" are determined by the annual costs of maintaining the NPP, upgrading and replacing equipment, and the amount of electricity generated during this period. At the same time, guaranteeing proper safety conditions is an absolute requirement for the operation of any nuclear power plant, regardless of its age. The choice of NPV (net present value) as an optimization criterion is logical and methodologically justified. This integral criterion compares multi-temporal indicators by discounting
, takes into account both economic and technical components. Being integral, i.e. taking into account the entire history of operation of the unit, NPV reflects the true ratio between investments in electricity generation (expenses) and the cost of electricity produced (result).

Clean discounted income defined as the sum of current effects for the entire billing period reduced to the initial step. The mathematical formulation of the problem of determining the service life according to the selected criterion is as follows:

https://pandia.ru/text/78/197/images/image021_16.gif" width="169" height="51">

Q(T)<QN,

Where k– time in years (may be less than one), N– calculation horizon; CFk is the effect (flow of payments) achieved on k-th step; ik– discount factor per step k; Q(T) is the safety level of the power unit, expressed by the number of incidents per year and generally depends on time; QN– normative level of safety.

The main approaches to the creation of a procedure for estimating the service life of the NPP EB are developed - an express method based on accounting for integral costs, which makes it possible to obtain an estimate of the service life (TL), taking into account both the economic component of operation and the technical condition of the EB - and a method for estimating the TL of an individual equipment, developed in the form of a Markov model, including the cost of repairs, equipment replacements, its reliability characteristics that change during operation, as well as the cost of downtime associated with the maintenance of this equipment. The decision to terminate the operation of the unit is made on the basis of an analysis of information about the equipment included in the group of critical elements, i.e. important from the point of view of safety.

The formula for calculating the cost of operating a power unit ( n types of equipment) has the form

PW(t) - the probability that the equipment is in working condition;

CWF- the cost of the replaced equipment or part thereof,

CFW- the cost of restoration work;

λ i(t) - equipment failure rate ;

μ i- intensity of recovery after failure.

CW =WITHE× N×D t, Where N- block power, CE– annual electricity tariff.

The resulting formula for estimating the cost of operating a power unit makes it possible to optimize its service life, taking into account all other aspects of operation.

To apply this approach, the issue of equipment selection, its ranking by the duration of downtime, the cost and significance of measures to manage the resource of specific equipment is essential.

One of the most typical tasks in diagnosing the technical condition of various NPP equipment is solving the problem of early recognition of equipment failure based on the analysis of changes in the controlled parameter. The effectiveness of the control system largely depends on the algorithm for processing information about the state of the controlled equipment. To obtain the most reliable decision about the presence of a process disorder, it is proposed to analyze not the initial random low-frequency process ξ t, and a function from it:

Weight coefficient" href="/text/category/vesovoj_koyeffitcient/" rel="bookmark">weight coefficients . After that, you can calculate the number of intersections of the process η t constant level S on a sliding time interval. The problem of optimizing the level for discord detection is set; for the first time, an analytical solution was obtained for the joint density of the distribution of the envelope of the first kind and its derivative; for the first time, an expression for the mathematical expectation of the number of intersections was obtained analytically N for the first derivative of the measured random process https://pandia.ru/text/78/197/images/image026_2.jpg" width="408" height="224">

Figure 4. Graphical display of the objective function

Third section devoted to the issues of predicting the resource of secondary circuit equipment by damage summation methods. Criteria of the limiting state and models of damage accumulation in the material of the equipment of the condensate-feeding tract are considered.

The aging of the material of one or another NPP equipment is accompanied by the accumulation of damage in the material of the equipment, which leads to a reduction in the residual life. The model for estimating the residual life is developed on the basis of the damage summation method proposed in the works

The relative age of a metal (i.e., accumulated quasi-static damage from prolonged exposure to slowly varying stresses, temperatures, and corrosive environments) can be defined as the sum of the ratios of equipment operating times under known conditions ti to the calculated maximum time to failure of this equipment under similar conditions τ i:

where each individual failure corresponds to the operation of the equipment for some time ti with known operational parameters, on which the time to failure τ depends i, and ω( t) - the relative age of the metal, due to work in several modes (where n- the number of modes by the moment of time t)

Then the probability of non-failure operation (FBR) can be defined as the probability of absenteeism ω( t) per level d=1, i.e., ω(0)=0, and ω( τ )=1.

A probability measure of damage has been introduced for various aging processes. For thin-walled equipment, which includes SG heat exchange tubes, nonlinear effects of damage accumulation are typical. Nonlinear damage summation models for estimating the residual life are built on the basis of the works.

Most of the problems of resource characteristics estimation are related to the problem of level crossing by a stochastic process of damage accumulation. An asymptotic approach to the calculation of the probability of no-failure operation based on the CLT is proposed. The method is applied to the accumulated damage in the bends of steam pipelines with a two-phase coolant due to drop impact erosion and in heat exchange tubes of a steam generator under conditions of stress corrosion cracking.

The drop impact erosion model is built on the basis of the phenomenological approach, when the damaging effect from moisture drops in a two-phase flow leads to erosion damage to the surface in a very small volume. The intensity of this process depends on the flow rate, pressure, temperature, steam moisture, material properties. The microdamage caused by the impact of a single drop is, in general, a random variable.

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11 about ECOLOI AND CH F.COM.

TECH1YULOG1IIGS1SOMU and NUCLEAR SUPERVISION

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About > | verge, gennn federal norms and instilled

in the field of the use of atomic energy “Requirements for the management of the resource of equipment and pipelines of nuclear power plants. Basic provisions»

In accordance with Article 6 of the Federal Law of November 21, 1995 -V 170-FZ "On the Use of Atomic Energy" (Collected Legislation of the Russian Federation. 1995, X® 48, Art. 4552; 1997, No. 7, Art. 808; 2001 , X® 29, 2949, 2002, X® 1, 2, X® 13, 1180, 2003, X® 46, 4436, 2004, X?35, 3607, 2006, X ® 52, item 5498, 2007, X® 7, C 834, No. 49, item 6079, 2008, X® 29, item 3418, X® 30, item 3616, 2009, No. 1, item 17; X® 52, item 6450; 2011. No. 29. item 4281; X? 30, item 4590, item 4596; X' 45, item 6333; X® 48, item 6732; No. 49, 7025; 2012, X* 26. 3446; 2013, X® 27, article 3451), subclause 5.2.2.1 of clause 5 of the Regulations on the Federal Service for Environmental, Technological and Nuclear Supervision, approved by Decree of the Government of the Russian Federation dated 30 July 2004 X® 401 (Collected Legislation of the Russian Federation, 2004, No. 32. Art. 3348; 2006, No. 5. Art. 544; No. 23, Art. 2527; X® 52. Art. 5587; 2008, A® 22, article 2581; No. 46, article 5337; 2009. X® 6, article 738; X" 33, article 4081; No. 49, article 5976; 2010, X* 9. Art. 960; X® 26, art. 3350; No. 38, Art. 4835; 2011, no. 6, art. 888; x? 14. Art. 1935; x? 41, art. 5750; No. 50, Art. 7385; 2012, .V® 29, art. 4123; X" 42, art. 5726; 2013, X® 12, art. 1343; X® 45, art. 5822; 2014, X® 2. Art. 108; X® 35, art. 4773; 2015, X® 2, Art. 491; X® 4 Art. 661)

Approve the attached federal norms and rules in the field of the use of atomic energy “Requirements for the management of the resource of equipment and pipelines of nuclear power plants. Basic Provisions” (NP-096-15).

L.V. Alyoshin

Supervisor

APPROVED by order of the Federal Service for Ecological, Technological _ and Nuclear Supervision dated "#" o2QSS, No. U / o

Federal norms and rules in the field of the use of atomic energy “Requirements for the management of the resource of equipment and pipelines of nuclear power plants. Basic Provisions»

I. Purpose and scope

1. These federal norms and rules in the field of the use of atomic energy “Requirements for the management of the resource of equipment and pipelines of nuclear power plants. Basic Provisions (NP-096-15) (hereinafter referred to as the Basic Provisions) were developed in accordance with Article 6 of the Federal Law of November 21, 1995 No. 170-FZ "On the Use of Atomic Energy" (Collected Legislation of the Russian Federation, 1995, No. 48 , item 4552; 1997, No. 7, item 808; 2001, No. 29, item 2949; 2002, No. 1, item 2; No. 13, item 1180; 2003, No. 46, item 4436; 2004, No. 35, item 3607; 2006, No. 52, item 5498; 2007, No. 7, item 834; No. 49, item 6079; 2008, No. 29, item 3418; No. 30, item 3616; 2009, No. 1, item 17; No. 52, item 6450; 2011, No. 29, item 4281; No. 30, item 4590, item 4596; No. 45, item 6333; No. 48, item 6732; No. 49 , article 7025; 2012, No. 26, article 3446; 2013, No. 27, article 3451), Decree of the Government of the Russian Federation dated December 1, 1997 No. 1511 "On approval of the Regulations on the development and approval of federal norms and rules in the field of Use of Atomic Energy” (Sobraniye Zakonodatelstva Rossiyskoy Federatsii, 1997, No. 49, Art. 5600; 1999, No. 27, Art. 3380; 2000, No. 28, Art. 2981; 2002, No. 4, Art. 325; No. 44, Art. 4392, 2003, No. 40, art. 3899; 2005, no. 23, art. 2278; 2006, no. 50, art. 5346; 2007, no. i, art. 1692; No. 46, art. 5583; 2008, no. 15, art. 1549; 2012, no. 51, art. 7203).

2. These Basic Provisions establish requirements for resource management of equipment and pipelines of nuclear power plants, classified in the designs of nuclear power plant units (hereinafter referred to as NPPs) in accordance with federal norms and rules in the field of the use of atomic energy to elements of 1, 2 and 3 safety classes.

3. These Basic Provisions apply in the design, construction, production, construction (including installation, adjustment, commissioning), operation (including service life extension), reconstruction (modernization), repair and decommissioning of the NPP unit.

4. The terms and definitions used are given in Appendix No. 1 to these Basic Provisions.

II. General provisions

5. These Guidelines apply to resource management of the following NPP equipment and pipelines:

all units of equipment and pipelines, classified in the design of the NPP unit as elements of the 1st safety class;

all pieces of equipment of single-unit and small-scale production and reference units of pipelines and NPP equipment, classified in the design of the NPP unit as elements of the 2nd safety class;

individual pieces of equipment and pipelines classified in the design of the NPP unit as elements of safety class 3 in the manner established by the operating organization in agreement with the developers of the designs of reactor plants (hereinafter - RP) and NPP.

6. In the design of the NPP unit for equipment and pipelines, their service life must be justified and assigned.

7. In the design (project) documentation for the NPP equipment and pipelines, resource limits must be established and justified.

characteristics and criteria for evaluating the resource. For NPP equipment and pipelines designed prior to the entry into force of these Basic Provisions, as well as in cases of termination of the activities of the equipment or pipeline designer, the justification and determination of the life characteristics of NPP equipment and pipelines must be performed by the operating organization.

8. NPP equipment and pipeline resource management should be based on:

a) compliance with the requirements of federal norms and rules in the field of the use of atomic energy, regulatory and guidance documents, instructions for the manufacture, installation, commissioning, operation, maintenance and repair, assessment of the technical condition and residual life of NPP equipment and pipelines;

b) maintaining NPP equipment and pipelines in good (operable) condition by timely detection of damage, implementation of preventive measures (inspections, repairs), replacement of worn-out NPP equipment and pipelines;

c) establishing mechanisms for the formation and development of defects that can lead to destruction or failure of NPP equipment and pipelines;

d) identifying the dominant (determining) mechanisms of aging, degradation and damage to NPP equipment and pipelines;

e) continuous improvement of monitoring of the processes of aging, degradation and damage to NPP equipment and pipelines;

f) the results of monitoring the technical condition and assessing the depleted and residual life of the NPP equipment and coarse piping based on the results of the monitoring;

g) mitigation (weakening) of the processes of aging, degradation and damage to equipment and pipelines through maintenance, repair, modernization, use of gentle modes

operation, replacement (when the resource is exhausted and the repair is impossible or inappropriate);

h) development and updating of the NPP equipment and piping resource management program.

9. The operating organization shall ensure the development and coordination with the developers of the RI and NPP designs of the NPP equipment and pipelines resource management program at the stage of their operation and carry out its implementation.

10. The resource management program for equipment and pipelines based on the resource assessment criteria established by design (design) organizations should be focused on preventing damage to NPP equipment and pipelines due to degradation and negative effects of aging of structural materials and the structures themselves during their operation.

11. The NPP equipment and pipeline resource management program should contain:

a) a list of NPP equipment and pipelines, the resource of which is subject to management, and resource characteristics to monitoring, indicating the controlled parameters for each piece of equipment and pipelines;

b) methods for monitoring the processes of damage accumulation in materials and structural elements of NPP equipment and pipelines due to aging, corrosion, fatigue, radiation, temperature, mechanical and other influences affecting the mechanisms of aging, degradation and failures of NPP equipment and pipelines;

c) the procedure for taking into account the technical condition of NPP equipment and pipelines, the actual characteristics of materials, loading parameters and operating conditions, and the procedure for adjusting working

operational control programs for the technical condition of NPP equipment and pipelines;

d) the procedure for the adoption and implementation of measures aimed at eliminating or mitigating damaging factors;

e) the procedure for accounting for the depleted and evaluation of the residual life of NPP equipment and pipelines;

f) the procedure for adjusting the maintenance and repair schedule (hereinafter referred to as MRO) in order to prevent irreversible manifestations of the mechanisms of aging and degradation of NPP equipment and pipelines.

12. Work programs for operational non-destructive testing of the state of the NPP equipment and pipelines metal and regulations for the maintenance and repair of NPP equipment and pipelines must take into account the provisions of the NPP equipment and pipelines resource management program.

13. The operating organization must ensure the collection, processing, analysis, systematization and storage of information throughout the entire service life of equipment and pipelines and maintain a database on damage, their accumulation and development, aging mechanisms, failures and disruptions in operation, as well as on operating modes , including transients and emergencies, in accordance with the NPP equipment and pipeline resource management program.

III. Preparatory measures for resource management of equipment and pipelines of nuclear power plants during design

and design

14. At the stage of designing and constructing NPP equipment and pipelines, NPP and RP project developers should develop a methodology for managing the life of NPP equipment and pipelines in the form of a set of organizational and technical measures based on predicting the mechanisms of damage to structural materials

NPP equipment and pipelines, monitoring resource characteristics and identifying the dominant aging and degradation mechanisms at the operational stage, periodically assessing the actual state of NPP equipment and pipelines and their residual life, corrective measures to eliminate or reduce aging and degradation mechanisms, formulating requirements for databases that provide implementation of the NPP equipment and pipeline resource management program.

15. Design (design) organizations should provide for measures and means to maintain the values ​​of resource characteristics within the limits that ensure the designated service life of NPP equipment and pipelines.

16. When choosing materials for NPP equipment and pipelines, the mechanisms of damage and degradation of materials (low- and high-cycle fatigue, general and local corrosion, intergranular and transgranular cracking, embrittlement, thermal aging, deformation and radiation damage, erosion, wear, change in physical properties) should be taken into account. ), the manifestation of which is possible during the design life of the plant equipment and pipelines, and for non-replaceable plant equipment and pipelines - during the life of the plant.

17. In cases where non-replaceable NPP equipment and pipelines must function during NPP decommissioning, the mechanisms of damage in the period of time, including NPP decommissioning, must be additionally taken into account. The remaining life of such NPP equipment and pipelines should be sufficient to ensure the decommissioning of the NPP.

18. For newly designed NPPs, the design (project) documentation for NPP equipment and pipelines must define a list of non-replaceable NPP equipment and pipelines, methods and

tools for monitoring parameters and processes that affect the resource characteristics of NPP equipment and pipelines.

19. For NPP equipment and pipelines of newly designed NPP units, design (project) documentation for NPP equipment and pipelines must contain:

a) a list of design modes, including normal operation modes (start-up, stationary mode, reactor power change, shutdown), abnormal operation modes and design basis accidents;

b) the estimated number of repetitions of all design regimes for the designated service life of NPP equipment and pipelines;

c) operating conditions and loads on equipment and

NPP pipelines;

d) list of potential mechanisms of damage and degradation

materials of NPP equipment and pipelines, which may affect their performance during operation (low- and high-cycle fatigue, general and local corrosion, intergranular and

transcrystalline cracking, embrittlement under the influence of temperature, neutron or ionizing radiation, thermal aging, creep, deformation damage, erosion, wear, formation and growth of cracks, taking into account the influence of the environment and creep, change in physical properties);

e) results of NPP equipment and pipelines strength and resource calculations, substantiation of their service life. The resource of non-replaceable NPP equipment and pipelines must be provided for the lifetime of the NPP unit and for the period of decommissioning of the NPP unit.

20. The design (project) documentation for NPP equipment and pipelines shall take into account the accumulated experience in operating NPP units, as well as experience in manufacturing, installation, and commissioning.

operation and decommissioning of NPP equipment and pipelines and the results of scientific research.

21. For newly designed NPP units, the design (project) documentation for NPP equipment and pipelines shall provide systems and (or) methods for monitoring the necessary parameters that determine the resource of NPP equipment and pipelines throughout their entire service life, from the following list:

temperature:

heating or cooling rate;

temperature gradients along the wall thickness;

pressure and rate of increase or release of pressure of the coolant or working media;

vibration characteristics;

temperature and humidity in the room where the equipment and (or) pipelines are located;

illumination intensity;

the degree of oxidation of the lubricant;

flow rate of the coolant or working media;

number of loading cycles;

changes in wall thicknesses;

radiation exposure;

the intensity of the electromagnetic field at the locations of the equipment and (or) pipelines;

movement of control points of NPP equipment and pipelines during heating or cooling down, as well as under external and (or) internal influences;

characteristics of external influences;

output signals of electronic units.

For NPPs under construction and in operation, a procedure for retrofitting NPP equipment and pipelines with systems and (or) methods for monitoring the necessary parameters from the above list shall be established.

22. The thicknesses of the walls of NPP equipment and pipelines, which are established during the design, must take into account the processes of corrosion, erosion, wear that occur during operation, as well as the results of predicting changes in the mechanical characteristics of materials due to aging by the end of the life of NPP equipment and pipelines.

23. The design (project) documentation for NPP equipment and pipelines shall provide for the possibility of their inspection, maintenance, repair, periodic monitoring and replacement (with the exception of non-replaceable NPP equipment and pipelines) during operation.

24. The design and layout of NPP equipment and pipelines should not interfere with the implementation of control, inspections, tests, sampling in order to confirm the predicted values ​​and rates of changes in resource characteristics associated with the mechanisms of aging and degradation of structural materials during the operation of NPP equipment and pipelines.

25. Design (design) organizations should develop methods for assessing and predicting the residual life of NPP equipment and pipelines. The RI and NPP designs shall provide for methods and technical means of operational control and diagnosing the state of NPP equipment and pipelines, maintenance and repair, allowing timely

Power plant equipment resource management as a tool for predicting the development of the electric power industry

A.P. Livinskiy

The electric power industry, being the basic branch of the Russian economy, provides for domestic needs National economy and the population in electricity, as well as the export of electricity to the CIS countries and far abroad.

In order to maximize effective use natural fuel and energy resources and the potential of the energy sector for long-term, stable supply of the country's economy and population with all types of energy The Government of the Russian Federation approved the Energy Strategy of Russia for the period up to 2020, which provides for:

• - reliable energy supply of the economy and the population of the country with electricity;
• - maintaining the integrity and development of the Unified Energy System of the country, its integration with other energy associations on the Eurasian continent;
• - improving the efficiency of functioning and ensuring the sustainable development of the electric power industry based on new, modern technologies;
• - reduction of harmful impact on the environment.

In the current edition of the Energy Strategy, more moderate levels of electricity consumption have been adopted, the pace of development of non-traditional and renewable energy sources and, first of all, hydropower has been increased, and more realistic commissioning of generating capacities and corresponding investments have been adopted.

In a favorable scenario, the development of the Russian electric power industry is oriented towards a scenario that implies the accelerated implementation of socio-economic reforms with the growth rate of gross domestic product production up to 5-6% per year and the corresponding steady growth in electricity consumption of 2.0-2.5% per year (Fig. 1 ). As a result, electricity consumption will reach 1290 by 2020 in the optimistic scenario, and 1145 billion kWh in the moderate scenario.

Taking into account the projected volumes of demand for electricity, under the optimistic scenario, the total production (Fig. 2) will increase compared to the reporting year 2002 by 1.2 times by 2010 (up to 1070 billion kWh) and more than 1.5 times by 2020 (up to 1365 billion kWh); with a moderate option for the development of the economy, respectively, 1.14 (up to 1015 billion kWh) and 1.36 times (up to 1215 billion kWh).

Rice. 1.

Rice. 2. Electricity generation at power plants in Russia (with moderate and optimistic options)

Rice. 3.

The production potential of the electric power industry in Russia (Fig. 3) currently consists of power plants with a total installed capacity of about 215 million kW, including nuclear power plants - 22 and hydroelectric power plants - 44 million kW, the rest is thermal power and power transmission lines of all voltage classes with a total length of 2 .5 million km. More than 90% of this potential is combined into the Unified Energy System (UES) of Russia, which covers the entire inhabited territory of the country from the western borders to the Far East.

According to the adopted Energy Strategy, there will be no significant changes in the structure of generating capacities: thermal power plants will remain the basis of the electric power industry; their share will remain at the level of 66-67%, nuclear power plants - 14%, the share of hydroelectric power plants will practically not change (20%).

At present, the main share (about 70%) in the structure of generating capacities is accounted for by thermal power plants operating on organic fuel (Fig. 4). As of January 1, 2003, the TPP's capacity was about 147 million kW. Almost 80% of the generating capacities of thermal power plants in the European part of Russia (including the Urals) operate on gas and fuel oil. In the eastern part of Russia, more than 80% work on coal. In Russia, there are 36 thermal power plants with a capacity of 1,000 MW or more, including 13 with a capacity of 2,000 MW or more. The capacity of the largest thermal power plant in Russia - Surgutskaya GRES-2 - is 4800 MW.

At thermal power plants, large power units of 150-1200 MW are widely used. The total number of such power units is 233 with a total capacity of about 65,000 MW.

Rice. 4.

A significant proportion of thermal power plants (about 50% of the capacity) are CHPPs, which are distributed throughout the country.

The main part (more than 80%) of the TPP equipment (boilers, turbines, generators) was put into operation in the period from 1960 to 1985 and by now has worked from 20 to 45 years (Fig. 5). Therefore, the aging of power equipment is becoming a key problem in the modern electric power industry, which will only get worse in the future.

Starting from 2005, there will be an increase in the volume of depleted park resource turbine equipment(Fig. 6). So, by 2010, 102 million kW (43%) of the currently operating equipment of TPPs and HPPs will have exhausted its fleet resource, and by 2020 - 144 million kW, which will be more than 50% of the installed capacity.

The decommissioning of turbine equipment that generates a fleet resource in the face of forecasted demand for electricity and capacity will lead to a capacity deficit of 70 GW at the level of 2005 (30% of demand), which by 2010 will amount to 124 GW (50% of demand) and by 2020 - 211 GW (75% of capacity demand) (Fig. 7).

Rice. 5.

Rice. 6. Forecast of volumes of turbine equipment working out the park resource

Rice. 7. Dynamics of Russia's balance in terms of capacity

Rice. 8.

power industry turbine equipment

Ensuring the increase in the demand for generating capacity is possible through the following main measures:

extending the life of existing hydroelectric power plants, nuclear power plants and a significant number of thermal power plants with the replacement of only the main components and parts;

completion of facilities that are in a high degree of readiness;

construction of new facilities in deficient regions;

modernization and technical re-equipment of thermal power plants using new, promising technical solutions.

To ensure the predicted levels of electricity and heat consumption in the optimistic and favorable scenarios, the commissioning of generating capacities at Russian power plants (taking into account the need to replace and modernize equipment that has exhausted its resource) for the period 2003-2020. approximately 177 million kW are estimated (Fig. 9), including 11.2 at hydroelectric power plants and pumped storage power plants, 23 at nuclear power plants, 143 at thermal power plants (of which 37 million kW are CCGTs and gas turbines), of which the commissioning of new generating capacities - about 131.6 GW, the volume of replacement of equipment that has exhausted its resource due to its technical re-equipment - 45.4 GW.

Rice. 9.

Rice. 10.

In the moderate scenario, inputs are estimated at about 121 million kW, including 7 at hydroelectric power plants and pumped storage power plants, 17 at nuclear power plants, and 97 at thermal power plants (of which 31.5 million kW are CCGTs and gas turbines).

At the same time, the total average inputs for Russia as a whole over the five-year period from 1991 to 2002 amounted to only 7 GW.

An important factor in the development of the electric power industry is the possibility of investments for new energy construction and technical re-equipment of existing power plants and electric networks, including complete replacement equipment that has worked out the park resource. The need for investments in the electric power industry for the period up to 2020, taking into account nuclear power plants, depending on the development option, is estimated at 140-205 billion US dollars, including 100-160 billion US dollars for generation (Fig. 10). Ensuring growth capital investments into the electric power industry with bringing them up to 4.0 billion dollars a year by 2005 and up to 6.0 billion dollars a year by 2010 (excluding nuclear power plants) is possible due to the introduction of an investment component in the tariff for electricity and thermal energy, creating favorable conditions for attracting foreign and domestic private investment through state guarantees, tax breaks, allocation of direct public investment, etc.

At the same time, in 2002, the volume of investments in the electric power industry, including nuclear power plants, amounted to $2.6 billion. In 2003, the expected volume of investments will be $3.6 billion.

In general, the total investments in the Holding for the five-year period from 1999 to 2003 amounted to 9 billion US dollars, or slightly more than 4% of the investment requirement for the period up to 2020.

To ensure the reliability of power supply to consumers, the power and electricity balances for the period up to 2020 should retain a significant share of equipment that has worked out its fleet resource (Fig. 11): in the period up to 2010, the volume of such equipment will increase to 93 GW with a subsequent reduction by 2020 up to 40 GW.

Rice. eleven.

Ensuring the predicted demand for electricity and capacity requires maintaining the operability of the equipment after it reaches the park resource.

This puts the task of resource management of power plant equipment to a qualitatively new level. The solution to this problem requires the creation of a data bank that makes it possible to predict the state of the equipment, develop a system of measures to maintain the operability of the equipment and monitor their implementation, and link proposals for extending the life of the equipment with prospective balances of power and electricity.

On fig. 12 shows the current scheme for organizing the life extension of equipment.

Rice. 12.

The park resource is understood as the operating time of elements of heat and power equipment of the same type in design, materials and operating conditions, which ensures their trouble-free operation in compliance with standard requirements for metal control, operation and repair of power plants.

To date, there has been an avalanche-like growth in capacities that have exhausted the park resource. The required volumes of replacement of equipment and their components were not provided with appropriate funding. There was a need to clarify the values ​​of the park resource in relation to specific equipment through a number of studies and activities.

In this regard, it was proposed to switch to an individual resource, i.e. the assigned resource of a particular object, determined taking into account the actual properties of the metal, geometric dimensions and conditions of its operation.

After the expiration of the design service life of the equipment, taking into account the restrictions established by regulatory documents, an analysis of its condition is carried out, based on the results of which a decision is made to replace or extend the service life of the equipment until the assigned individual resource is exhausted, which is determined by a set of measures within the resource extension system.

The system for extending the life of equipment in the electric power industry is based on:

1. On federal laws:

“On industrial safety of hazardous production facilities”;

“On technical regulation”;

“About Licensing certain types activity."

2. On the Decrees of the Government of the Russian Federation:

“On the procedure and conditions for the application technical devices at a hazardous production facility”;

“On the procedure for organizing and exercising production control over compliance with industrial safety requirements at a hazardous production facility”;

“On measures to ensure industrial safety of hazardous production facilities on the territory of the Russian Federation”;

3. On normative documents Gosgortekhnadzor of Russia:

“General industrial safety rules for organizations operating in the field of industrial safety of hazardous production facilities”;

“Rules for the examination of industrial safety”;

“Regulations on the procedure for extending the period of safe operation of technical

devices, equipment and structures at hazardous production facilities”;

“Standard instruction for metal control and service life extension of critical elements of boilers, turbines and pipelines of thermal power plants”.

Preparation of a decision to extend the service life, taking into account all options, requires a serious technical and economic analysis based on the technical condition of the power plant and the prospects for its development (technical re-equipment).

In accordance with the requirements of the Standard Instructions... and Regulations..., AO-energy and AO-power plants independently or with the involvement of organizations monitor the technical condition of the equipment and conduct studies of the strength characteristics of the metal.

Such studies are usually carried out by expert organizations (Fig. 13). Their conclusions together with the decision of AO-energo and AO-power plant

about extending the life of the equipment are sent, in accordance

With Model Instructions..., at OAO RAO UES of Russia. The Department of Scientific and Technological Policy and Development of RAO UES of Russia, with the involvement of industry research organizations, analyzes the submitted materials, makes a conclusion on the possibility and terms of further operation of the equipment. Based on the decision of AO-Energo and AO-Power Plants, conclusions specialized organization The Department of Scientific and Technical Policy and Development of JSC RAO UES of Russia approves (or does not approve, or approves with restrictions) the decision of AO-Energo and AO-Power Plants on the possibility and terms of further operation of the equipment.

Rice. 13.

Approval by RAO UES of Russia of the decision of AO-energo and AO-power plant is the basis for the Gosgortekhnadzor of Russia to register the conclusion of the industrial safety expertise and grant the power plant the right to further operate the equipment.

The main directions for improving the organization of work to extend the service life of equipment (Fig. 14) will be related to:

• - with the improvement of the directive (determined by the documents of the Gosgortekhnadzor of Russia) part of these works;
• - with giving economic interest in the results of these works, including works to determine the commercial resource and reliability of the power plant for various organizations(SO-CDU, ATS, equipment manufacturers, etc.).

To do this, it is planned to improve the organization of the extension in the next.

1. Control of the state of metal and equipment of TPP is entrusted to testing laboratories and non-destructive testing laboratories accredited by the Gosgortekhnadzor of Russia. Accreditation should be carried out taking into account the recommendations of the Department of Scientific and Technical Policy and Development of RAO UES of Russia, further through NP INVEL ( Non-commercial partnership"Innovations in the electric power industry").

Rice. 14.

• 2. Expert organization, which considers materials on extending the service life of equipment and makes a conclusion regarding the service life, should be independent and appointed by the Department of Scientific and Technical Policy and Development of JSC RAO UES of Russia and, in the future, NP INVEL
• 3. The Department of Science and Technology Policy and Development of JSC RAO UES of Russia (hereinafter NP INVEL) must organize work to assess the commercial life and reliability of power plants and determine permanent organizations interested in such information.

From the presented materials it is clear that in the foreseeable future, in the face of a lack of investment in new construction, the shortage of generating capacities will grow. The main source of its coverage will be the extension of the service life of existing equipment. For this, it is necessary to develop organizational mechanism resource management, which should correspond to the new realities that are emerging in the electric power industry in connection with its reform. important organizational aspects are the following:

improvement of regulatory and technical documentation that ensures reliable and safe operation of equipment;

monitoring equipment damage, preparation of standard technical and organizational solutions to extend the life of equipment (circulars, information letters);

creation of a database for its operation;

reducing the cost of monitoring and repairing equipment.

All these activities will improve the resource management mechanism and make it important tool forecasting the further development of the electric power industry.

The first steps in this direction have already been taken. So, on the instructions of the DNTPiR of JSC RAO UES of Russia, the Teploelektroproekt Institute is preparing “Proposals for extending the service life of thermal power plant equipment beyond the park”, which include:

• - forecast of the technical condition of thermal power plants working out the park resource in the period up to 2008;
• - development of station proposals for technical events, allowing to extend the life of equipment beyond the park;
• - assessment of financial costs for the implementation of measures to extend the life of the equipment;
• - organization of resource management of power plant equipment in the context of reforming the electric power industry.

As part of this work, a study was made of the state of equipment in all seven regions of Russia with an installed capacity of 131.422 million kW. Its results are used in the development of a five-year corporate power balance for the period 2004-2008.

As the analysis showed, by 2008 the individual resource will be exhausted on equipment with an installed capacity of 10.929 million kW, which is 9.1% of the installed capacity of TPPs of RAO UES of Russia Holding. This will require significant investment in work to extend the life of the equipment.

A particularly large amount of work to extend the life of equipment and costs falls on the UES of the Urals, one of the most energy-intensive regions of Russia. For the period 2004-2008. the cost of measures to extend the resource in this region will amount to 6567.7 million rubles, the volume of renewable capacity will be 5034 MW, and the peak of the required investments will be in 2007-2008.

In general, at TPPs of Russia for the period 2004-2008. it will be necessary to carry out a set of measures to ensure the extension of the life of the equipment, total amount, including VAT, 19.58 billion rubles. (at current prices). At the same time, the unit cost of the extended capacity will be 1,792.1 rubles/kW ($58.8/kW).

When forecasting power balances for a longer period (10-15-20 years), additional studies should be carried out to determine the nature of the change in the costs of extending the life of thermal power plant equipment.