DEVELOPMENT OF A DISTRIBUTED INFORMATION AND COMPUTING CONTROL SYSTEM FOR THE NUCLEAR UNIT AT NOVOVORONEZH NPP

Author(s):  
Д.С. Синюков ◽  
А.Д. Данилов ◽  
А.А. Самодеенко ◽  
А.А. Иванников

Ядерные блоки атомных электростанций имеют длительный срок эксплуатации, что приводит к ситуации, когда в процессе эксплуатации технические и программные средства систем управления перестают отвечать текущим современным требованиям в плане надежности и безопасности их использования. В результате для продления срока действия ядерного блока требуется обязательное проведение модернизации информационно-вычислительной системы (ИВС) управления. Приводятся результаты такой работы, проведенной на 4 блоке Нововоронежской АЭС. При выборе оборудования для создания новой ИВС модернизируемого энергоблока был реализован принцип унификации. Программное обеспечение всех компонентов программно-технического комплекса ИВС, включая функции систем предоставления параметров безопасности и внутриреакторного контроля, реализовано на единых программных средствах. Представленные значения параметров сигналов на всех рабочих станциях программно-технического комплекса информационной системы, интерфейсы взаимодействия, человеко-машинный интерфейс и навигация по видеокадрам идентичны, что учитывает требования по оптимальному взаимодействию системы «человек-машина». Система удовлетворяет требованиям по обеспечению надёжности на основе резервирования, независимости, разнообразия, с учётом отказов по общей причине. Для этого ИВС была реализована в виде двухканальной информационной системы. Основной и дублирующий каналы измерения и обработки данных в программно-техническом комплексе ИВС функционируют одновременно в полном объеме. Разработанная информационно-вычислительная система позволила продлить срок эксплуатации 4 энергоблока Нововоронежской АЭС на 15 лет Nuclear units of nuclear power plants have a long service life, which leads to a situation when, during the operation, the technical and software tools of control systems no longer meet the current modern requirements in terms of reliability and safety of their use. As a result, in order to extend the validity period of the nuclear unit, mandatory modernization of the information and computing system (ICS) of management is required. This article presents the results of such work carried out at Unit 4 of the Novovoronezh NPP. When choosing the equipment to create a new ICS of the upgraded power unit, we implemented the principle of unification. The software of all components of the ICS software and hardware complex, including the functions of systems for providing security parameters and in-reactor control, is implemented on unified software tools. The representation of signal parameter values at all workstations of the software and hardware complex of the information system, the interfaces of human-machine interface interaction and navigation through video frames are identical, which takes into account the requirements for optimal interaction of the man-machine system. The system meets the requirements for ensuring reliability based on redundancy, independence, diversity, taking into account failures for a common reason. For this purpose, we implemented the ICS in the form of a two-channel information system. The main and backup channels of measurement and data processing in the ICS software and hardware complex function simultaneously in full. The developed information and computing system made it possible to extend the service life of 4 power units of the Novovoronezh NPP for 15 years

Sensors ◽  
2021 ◽  
Vol 21 (12) ◽  
pp. 3976
Author(s):  
Sun Jin Kim ◽  
Myeong-Lok Seol ◽  
Byun-Young Chung ◽  
Dae-Sic Jang ◽  
Jonghwan Kim ◽  
...  

Self-powered wireless sensor systems have emerged as an important topic for condition monitoring in nuclear power plants. However, commercial wireless sensor systems still cannot be fully self-sustainable due to the high power consumption caused by excessive signal processing in a mini-electronic computing system. In this sense, it is essential not only to integrate the sensor system with energy-harvesting devices but also to develop simple data processing methods for low power schemes. In this paper, we report a patch-type vibration visualization (PVV) sensor system based on the triboelectric effect and a visualization technique for self-sustainable operation. The PVV sensor system composed of a polyethylene terephthalate (PET)/Al/LCD screen directly converts the triboelectric signal into an informative black pattern on the LCD screen without excessive signal processing, enabling extremely low power operation. In addition, a proposed image processing method reconverts the black patterns to frequency and acceleration values through a remote-control camera. With these simple signal-to-pattern conversion and pattern-to-data reconversion techniques, a vibration visualization sensor network has successfully been demonstrated.


Author(s):  
Nikolay A. Makhutov ◽  
Mikhail M. Gadenin ◽  
Sergey V. Maslov ◽  
Dmitry O. Reznikov ◽  
Sergey N. Pichkov ◽  
...  

Materials ◽  
2021 ◽  
Vol 14 (18) ◽  
pp. 5258
Author(s):  
Cyril Zimmer ◽  
Yashashwini Nikhitha Rallabandi ◽  
Klaus Szielasko ◽  
Christian Eichheimer ◽  
Michael Luke ◽  
...  

Reactor safety research aims at the safe operation of nuclear power plants during their service life. In this respect, Fraunhofer IZFP’s micromagnetic multiparameter, microstructure, and stress analysis (3MA) has already made a significant contribution to the understanding of different aging mechanisms of component materials and their characterization. The basis of 3MA is the fact that microstructure and mechanical stress determine both the mechanical and magnetic material behavior. The correlation between features of magnetic and mechanical material behavior enables the micromagnetic prediction of mechanical properties and stress, both of which can decisively influence the service life. The Federal Ministry for Economic Affairs and Energy (BMWi) funded this research, handling the mutually superimposed microstructural and stress-dependent influences, a substantial challenge, especially under practical conditions. This superposition leads to ambiguities in the micromagnetic features. The 3MA testing system has been extended by more sophisticated evaluation methods being able to cope with more complex datasets. Investigations dealing with the expansion of the feature extraction and machine learning methods have led to a more precise distinction between microstructural and stress-dependent influences. This approach provides the basis for future applications in reactor safety.


Author(s):  
Y.S. Nurakhov ◽  
A.E. Kami

The article presents the development of an information system for recognizing voice into text for people with hearing impairments, which makes it possible to improve the quality of life and interaction in society with other people. The device, software, functional blocks and subsystems of the information system are described. Examples of possible application and placement of the system in various spheres of public life are given. One of the types of implementation of the voice recognition information system is described. The development and creation of prototypes of a device for people with hearing impairments is considered. In the course of the research, the Google Speech Api technology was selected for speech recognition. In addition, this article presents a software and hardware complex that allows you to translate speech into text and then display it on the screen. Arduino UNO-based devices were chosen to achieve the goal. All information is processed on the smartphone of people with hearing impairments, which is sent to the device via Bluetooth with Arduino.


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

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


Author(s):  
John M. O'Hara

The performance of complex systems, such as power plants and commercial aircraft, is based on the integration of human, software, and hardware elements. They are designed to operate safely under normal and disturbance conditions. Ideally one would validate that safety and productivity goals can be achieved prior to actual operation. While some types of systems can be tested in actual operational environments, validation is especially difficult when safety or economic considerations preclude testing the types of disturbance conditions that the integrated system is designed to handle. Thus the conceptual and methodological challenges to validating such systems are significant and new approaches are emerging. The papers in this symposium will describe approaches taken to validation using examples from commercial nuclear power, civil aviation, military, and medical systems.


Author(s):  
Jaroslav Pachner ◽  
Inna V. Kaliberda

By 2010, fifteen Russian nuclear power plant (NPP) units will reach the end of their scheduled service life of 30 years. An extension of NPP operation beyond the scheduled service life, which is provided for by the Russian safety standard OPB-88/97, requires a renewal of the plant operating license by the regulatory organization Gosatomnadzor (GAN). This paper presents an overview of an IAEA project aimed at assisting GAN in the development of a set of regulatory guidelines for NPP license renewal/life extension. The overview includes a description of the Russian regulatory strategy for life extension of NPPs and IAEA activities to facilitate drafting and application of the regulatory guidelines using international experience.


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