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This book presents a comprehensive overview of the computerized core monitoring techniques currently employed at pressurized water reactor (PWR) and boiling water reactor (BWR) nuclear power plants. It also offers a brief overview of the corresponding techniques at research and materials testing reactors. The book combines detailed descriptions of the theoretical background and fundamental underlying principles as well as the practical applications of core surveillance. It not only provides numerous industrial examples to illustrate how complex computerized systems are able to support the safe operation of nuclear reactors, but also outlines some new application areas that were made possible only by state-of-the-art computing resources. Thanks to its practical approach, it serves as a valuable and practical reference book for readers interested in the surveillance of nuclear reactors, ranging from undergraduate and postgraduate students to researchers and experts working at research reactors and nuclear power plants, as well as at nuclear regulatory authorities.
This report extends the application of on-line monitoring to equipment and process condition monitoring, encompassing an array of technologies including vibration monitoring, acoustic monitoring, loose parts monitoring, motor current signature analysis and noise diagnostics, as well as vibration analysis of the reactor core and the primary circuit. Furthermore, this report includes the application of modeling technologies for equipment and process condition monitoring. A majority of these technologies depend on existing data from existing sensors and first principles models to estimate equipment and process behavior using empirical and physical modeling techniques. In doing so, pattern recognition tools such as neural networks, fuzzy classification of data, multivariate state estimation and other means are used. These means are described in the report, and examples of their application and implementation are provided. The benefits of OLM for performance verification of process instruments were described in the first report and included such advantages as the ability to extend the calibration interval of pressure, level and flow transmitters, detection of blockages, voids and leaks in pressure sensing lines, detection of degradation of the dynamic response of process instruments, and the like. Examples of benefits of OLM for condition monitoring include: (1) the ability to determine the onset of failure of pumps, valves, motors and reactor vessel components; (2) residual life assessment of equipment; (3) equipment life extension and aging management; (4) the ability to establish objective schedules for preventive maintenance, equipment refurbishment or replacement; and (5) maintenance cost reduction, efficiency improvements, reduction of plant outages, and reduction of radiation exposure to plant personnel.--Publisher's description.
Covers the mechanical, chemical, thermal, hydraulic, neutronic and irradiation considerations important to the safe design of a nuclear reactor core. The core features of commonly used reactor types including light and heavy water reactors, as well as gas cooled reactors, are addressed.
This publication makes recommendations concerning safety features for incorporation into the design of the reactor core for a nuclear power plant, taking account of recent developments in the design of the reactor core and including guidance on general and specific design considerations. It supersedes IAEA Safety Series No. 50-SG-D14.
Today, businesses need a new type of system that can remain responsive at all times. This result is achievable and is called reactive, which means it reacts to changes. The development of such systems is a complex task, requiring a deep understanding of the domain. The developers of the Spring Framework help with the reactive version
Gas-cooled, graphite-moderated nuclear reactors suffer ageing and degradation to the graphite during service posing a threat to the functionality of the core, and potentially, the safe operation of the reactor. Thus, the importance of modelling and measuring reactor core graphite properties and performance increases especially as continued use beyond the designed life time becomes significant. This book captures the proceedings from the third in a series of meetings addressing the extensive research and analysis performed to ensure the continuing safe performance of the graphite cores. Covering four broad themes: mechanistic; statistical; empirical; and, plant performance, this book should appeal to a broad range of readers from engineers and reactor operators to policy makers.
The reactor core is the central part of a nuclear reactor where nuclear fission occurs. It consists of four basic systems and components: the fuel (including fuel rods and the fuel assembly structure), the coolant, the moderator and the control rods, as well as additional structures such as reactor pressure vessel internals, core support plates, and the lower and upper internal structure in light water reactors. This Safety Guide provides recommendations on meeting the safety requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, applied to the design of the reactor core for nuclear power plants. The publication addresses the safety aspects of the core design and includes neutronic, thermohydraulic, thermomechanical and structural mechanical aspects. Other aspects considered are those relating to reactor core control, shutdown and monitoring, and core management.