The drive of the reactor control and protection system (CPS) is a system of normal operation, important for safety. Malfunctions of the drives of the ARC type CPS are often the initial events for accidents leading to unauthorized downtime. The currently existing standard methods for monitoring the parameters of the CPS do not allow for a reliable assessment of the condition of the drives. In this paper, it is proposed to implement an approach that provides an increase in sensitivity when recognizing the states of the drives of the ARC control system by processing the initial signals, which are vibroacoustic signals registered on the lid of the upper unit of the VVER reactor. A procedure for processing diagnostic signals using singular spectrum analysis is proposed. The proposed approach differs from the known ones by the presence of a scaling procedure, which is implemented by multiplying the eigenvalue matrices by the gankelized matrices of the source data. Due to scaling, the necessary sensitivity increase is provided. The expected increase in sensitivity is based on the fact that the eigenvalues reflect the structure of the signals, which changes significantly under the influence of the defect. The proposed method was used to process vibroacoustic signals registered on the lid of the upper block of the VVER reactor unit. Experimental studies were carried out at the test stand of Izhorskiye Zavody OJSC. The results of processing experimental data indicate a high quality of diagnosis. The hypothesis was clearly confirmed that the difference in the structure of diagnostic signals of serviceable and faulty equipment can manifest itself in the eigenvalues of the gankel signal matrices. The approach proposed in the article to the processing of diagnostic signals is easily amenable to automation and can be implemented in the development of a diagnostic system for the drive of an ARC-type CPS.
The paper deals with results of hardware-software complex application in nuclear power units design tasks and control. Critical analyses of existing information systems applied in the global power engineering was made. It was demonstrated that the main task, to be solved, was aimed at parameters monitoring and not processes control in complex. Moreover, all existing systems have distinguished functions resulting in high information load on operating personnel if there is no established managerial decision. Authors proposed the approach based on the power unit software model and respective mathematical simulation hardware for the operating personal support system development and nuclear power units facilities designing. A list of function for such systems was developed. It is demonstrated that the basis of functioning in technological process control tasks is the power unit simulation model enabling modelling under different operation modes. The power unit of the state-of-the art nuclear facility evolves a complicated technical system. For presentation of the power unit formal structure an oriented graph is used. Mathematical model of the power unit process flow diagram presents formalized record of the system digital and logic variables. The power unit model includes a distributed dynamic neutronics reactor core model, one dimension two-phase thermal physical model of processes in the main power unit systems, I&C model. The approach of the software model integration in the design freeze tasks is shown.
This article is focused on the current issue of developing an operator information support system (OISS) for the Novovoronezh NPP II project. One of the main reasons to raise this topic is the MCR operator’s overload with data due to the greatly increased information flows related to the VVER-1200 Process I&C compared to the serially produced VVER-1000 power units. The other important reason, in the authors’ opinion, is the increased volume of existing procedures in hard copy due to the strengthened requirements for their registration and attempts to describe all possible failures and deviations in the programs and plant evolution sheet, which complicates the work on them. In the era of ubiquitous digitalization, the paper procedures can only distract the attention of the operator, who is overloaded with information even without that. The obvious solution is to create a system providing automatic collection and analysis of information. In addition, the functionality of the operator information support system allows the use of operating experience, thus minimizing the impact of the human factor. The lack of knowledge or experience could be especially challenging with procedures being applied infrequently, for example, for starting up and shutting down the unit. The authors consider the development and functionality of interactive procedures and applicable requirements for them. Particular attention is paid to the ergonomics of the workplace and the convenience of operating personnel working with an interactive procedure. Since the transition from the paper version of the programs can cause problems with reading the procedures and, ultimately, lead to the failure of the unit start-up time, the personnel of the operating station were directly involved in the development of the interactive programs. Based on the review results, conclusions were made about the correctness of the approaches in developing the interactive procedures and validated solutions to be disseminated for all routine operations.
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