Operational Control of a Power Unit of a Nuclear Power Plant
Major: Nuclear Рower Еngineering
Code of subject: 7.143.01.O.003
Department: Heat Engineering and Thermal and Nuclear Power Plants
Lecturer: Associate Professor, Ph. D. Matiko Halyna Fedorivna
Semester: 1 семестр
Mode of study: денна
Завдання: The study of an educational discipline involves the formation of competencies in students of education: general competences: ZK1: the ability to learn and master modern knowledge; ZK3: ability to apply knowledge in practical situations; ZK4: skills in using information and communication technologies; professional competences: FC1: the ability to apply appropriate quantitative and qualitative modern scientific and technical methods and computer software to solve complex engineering tasks in the field of nuclear energy; FK3: the ability to apply the acquired specialized conceptual knowledge and skills in the design and operation of equipment and systems, as well as the reactor installation as a whole; FK7: ability to manage projects and evaluate their results; FK12: ability to demonstrate understanding of quality and safety management issues in the nuclear power industry; FCS1.2: the ability to use knowledge of technologies and technical means used to control a nuclear reactor.
Learning outcomes: PR2: the ability to demonstrate specialized conceptual knowledge of atomic energy, acquired in the process of study and/or professional activity, including knowledge and understanding of the latest achievements, which provide the ability for innovative and research activities. PR6: the ability to use modern technologies, equipment, information management tools to solve complex engineering tasks and problems of nuclear energy. PR14: the ability to choose and use methods and means of measurement to determine the values ??of technological parameters of processes and operating modes of nuclear energy equipment in accordance with the standards and requirements of the metrological service of Ukraine. PR1.2: demonstrate an understanding of the physical processes that are relevant to power management of a nuclear reactor at a nuclear power plant; understanding of modern technologies used to control a nuclear reactor; application of technical means used to control a nuclear reactor. Lecture, practical and laboratory classes: information-receptive method, reproductive method, heuristic method, laboratory classes: research method, independent work: reproductive method. Current control: oral survey; performances in classes, practical work, presentation of reports, essays and presentations, tests, assessment of activity, submitted proposals, original solutions, etc. Examination control: written and oral survey, test control.
Required prior and related subjects: • Nuclear Power Plants, Part 1, 2 • Auxiliary equipment and pipelines of nuclear power plants, • Automated control systems for technological processes at nuclear power plants • Non-stationary processes in nuclear reactors
Summary of the subject: The discipline provides for the study of the basic principles of the organization and management of the NPP operation process, in particular the operational and dispatching management of the NPP, the typical organizational structure of the NPP operation management, the functions and tasks of the NPP operation management system, the stages of training and work of the operational personnel of the NPP. The structure and functions of the automated system for controlling the technological process of the NPP power unit, the principles of the organization of NPP control boards are considered. The organization of the management of the NPP power unit in different modes of operation, management of the main technological units and systems of the NPP power unit is considered. Special attention was paid to the study of systems important for the safety of the nuclear power plant with the VVER-1000 reactor. In particular, the reactor control and protection system, the internal reactor control system, the hydraulic storage system, the high-pressure active zone emergency cooling system, the high-pressure boron emergency injection system, the boron concentrate system, the emergency gas removal system from the first circuit, the pressure compensation system of the first circuit, the system steam discharge devices, etc. Management tasks in different operating modes of these systems are analyzed.
Опис: INTRODUCTION. BASIC TERMS AND DEFINITIONS. ORGANIZATION AND MANAGEMENT OF THE NPP OPERATION PROCESS Structure of SE NAEK "Energoatom". Operational and dispatching management of the NPP. Typical organizational structure of NPP operation management. Functions and tasks of the NPP operation management system. Training of NPP operational personnel. AUTOMATED SYSTEM FOR CONTROLLING THE TECHNOLOGICAL PROCESS OF A NPP POWER UNIT Purpose and structure of the control system of the NPP power unit. Functions and types of automatic control systems. Subsystems of the control system of the power unit. NPP control panels. Organization of the control block board. ORGANIZATION OF THE MANAGEMENT OF A NPP POWER UNIT IN DIFFERENT OPERATION MODES General issues of power unit management. NPP operating modes and requirements for control systems. Management of the mode of operation of units when supplying electricity to the network. The main tasks of regulation of the power unit. Static programs for regulating the parameters of a power unit with a VVER reactor. MANAGEMENT OF MAIN TECHNOLOGICAL UNITS AND SYSTEMS OF A NPP POWER UNIT General information about NPP power unit systems. Description of the technological scheme of the power unit with the VVER reactor. REACTOR CONTROL AND PROTECTION SYSTEM Purpose and functions of the system. Regulators of the reactor's control system and their effectiveness. The structure of the VVER-1000 series SUS. Neutron flow control equipment. Regulation of reactor power. INTERNAL-REACTOR CONTROL SYSTEM (ISVR) Appointment of SVRK. Functions of SVRK. Structure of SVRK. The structural diagram of the standard SVRK VVER-1000. Direct charge detectors. Temperature control sensors. EMERGENCY COOLING SYSTEMS OF THE REACTOR ACTIVE ZONE. SYSTEM OF HYDRAULIC CAPACITIES HIGH PRESSURE ACTIVE ZONE EMERGENCY COOLING SYSTEM HIGH PRESSURE BORING EMERGENCY INPUT SYSTEM BORON CONCENTRATE SYSTEM PURGE-FEED SYSTEM OF THE FIRST CIRCUIT FIRST CIRCUIT PRESSURE COMPENSATION SYSTEM EMERGENCY GAS REMOVAL SYSTEM FROM THE FIRST CIRCUIT SYSTEM OF STEAM DISCHARGE DEVICES EMERGENCY FOOD WATER SYSTEM AUXILIARY FOOD WATER SYSTEM OTHER SYSTEMS IMPORTANT FOR THE SAFETY OF NPP WITH VVER-1000 REACTORS Main condensate system. Steam generator purge system. System of chemically desalinated water and emergency feeding of deaerators. Backup cooling system through the second circuit. System of emergency and scheduled low-pressure cooling. Auxiliary systems of the main circulation pump.
Assessment methods and criteria: Current monitoring of practical and laboratory classes is carried out in order to identify the student's readiness for classes in the following forms: • oral survey before the start of classes; • assessment of the student's activity in the course of classes, submitted proposals, original solutions, clarifications and definitions, additions to previous answers, etc.; • surveys and reports during practical and laboratory classes. • protection of laboratory works, evaluation of reports for laboratory works. Examination control is carried out in the form of a written and oral survey and/or test control. The final control is carried out based on the results of the current control and semester examination control
Критерії оцінювання результатів навчання: Current control (PC) - 30 points Examination control - 70 points Total for the discipline - 100 points
Порядок та критерії виставляння балів та оцінок: 100–88% – awarded for a high level of knowledge (some inaccuracies are allowed) of the educational material of the component contained in the main and additional recommended literary sources, the ability to analyze the phenomena being studied, in their relationship and development, clearly, succinctly, logically , consistently answer questions, ability to apply theoretical provisions when solving practical problems; 87–80% – awarded for knowledge of the educational material of the component above the average level, including calculations, reasoned answers to the questions asked (a small number of inaccuracies are possible), the ability to apply theoretical provisions when solving practical problems; 79–71% – a generally correct understanding of the educational material of the component, including calculations, reasoned answers to the questions, which, however, contain certain (insignificant) shortcomings, is awarded for the ability to apply theoretical provisions when solving practical problems; 70–61% – awarded for mediocre knowledge of the educational material of the component, poorly reasoned answers, weak application of theoretical provisions when solving practical problems; 60–50% – awarded for weak knowledge of the educational material of the component, inaccurate or poorly reasoned answers, with a violation of the sequence of presentation, for weak application of theoretical provisions when solving practical problems; 49–26% – is presented for ignorance of a significant part of the educational material of the component, significant errors in answering questions, inability to apply theoretical provisions when solving practical problems; 25-00% - awarded for ignorance of a significant part of the educational material of the component, significant errors in answering questions, inability to navigate when solving practical problems, ignorance of the main fundamental provisions, failure to complete the task.
Recommended books: 1. Ostreikovskyi V. A. Exploitation of nuclear power plants: A textbook for high schools. - Moscow: Energoatomizdat. - 1999. - 928 p. 2. Yastrebenetskyi, M. A. and others. Control and protection systems for nuclear reactors. - K: Basis-Print. - 2011 - 768 p. 3. Demchenko V. A. Automation and modelling of technological processes of nuclear power plants and thermal power plants. Tutorial/ Publishing house "Astroprint". Odesa - 2001. - 305 p. 4. Behun V. V. Descriptions of systems important for the safety of the NPP with the reactor WWER-1000. A manual for students of technical universities of Ukraine/ Publishing house of NTUU "KPI". K. - 2009. - 297 p.
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