Remote Monitoring and Control of a Simulated Nuclear Reactor


Book Description

The advent of the Internet has molded an undergraduate student body that garners understanding through hands-on experiences. Thus, engineering academia has reached a turning point and it must adapt to better serve its future pupils. Specifically, nuclear engineering education lacks much of the interactive tools which have been made available to other branches of engineering. The primary objective of this thesis is to develop an interactive tool to aid in teaching the fundamentals of nuclear reactor theory and power plant operation. To achieve this goal, an interactive, real-time system for monitoring and controlling a simulated, commercial pressurized water reactor (PWR) was created. Well-tested mathematical models for reactor neutronics, thermodynamics, and synchronous machines were integrated to create an overall dynamic system model for the plant on a low-cost single board computer (Raspberry Pi). Techniques in network communication were then applied to establish wireless access to the simulation controls using Node-RED. Finally, hardware elements were incorporated to enhance the interactive feeling of the program.







Review of Fuel Failures in Water Cooled Reactors


Book Description

The purpose of this report is to provide a combined presentation of the worldwide experience gained on fuel failures in water cooled reactors and to give statistical data on fuel failures for the period 1987 to 1994. It contains detailed descriptions of primary and secondary failure mechanisms which occurred in 'western' type boiling and pressurized water reactors (BWRs and PWRs), Soviet type pressurized light water reactors (WWERs) and Canadian type heavy water reactors (CANDUs). It also includes information on detection, examination and analysis of fuel failures as well as on fuel failure prevention and management in plant operation.




Nuclear Safety


Book Description




Fuel Management and Handling


Book Description

Covers advances in nuclear fuel handling and fuel management and assesses their impact in increasing reactor availability




Understanding and Mitigating Ageing in Nuclear Power Plants


Book Description

Plant life management (PLiM) is a methodology focussed on the safety-first management of nuclear power plants over their entire lifetime. It incorporates and builds upon the usual periodic safety reviews and licence renewals as part of an overall framework designed to assist plant operators and regulators in assessing the operating conditions of a nuclear power plant, and establishing the technical and economic requirements for safe, long-term operation. Understanding and mitigating ageing in nuclear power plants critically reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC), along with their relevant analysis and mitigation paths, as well as reactor-type specific PLiM practices. Obsolescence and other less obvious ageing-related aspects in nuclear power plant operation are also examined in depth. Part one introduces the reader to the role of nuclear power in the global energy mix, and the importance and relevance of plant life management for the safety regulation and economics of nuclear power plants. Key ageing degradation mechanisms and their effects in nuclear power plant systems, structures and components are reviewed in part two, along with routes taken to characterise and analyse the ageing of materials and to mitigate or eliminate ageing degradation effects. Part three reviews analysis, monitoring and modelling techniques applicable to the study of nuclear power plant materials, as well as the application of advanced systems, structures and components in nuclear power plants. Finally, Part IV reviews the particular ageing degradation issues, plant designs, and application of plant life management (PLiM) practices in a range of commercial nuclear reactor types. With its distinguished international team of contributors, Understanding and mitigating ageing in nuclear power plants is a standard reference for all nuclear plant designers, operators, and nuclear safety and materials professionals and researchers. Introduces the reader to the role of nuclear power in the global energy mix Reviews the fundamental ageing-degradation mechanisms of materials used in nuclear power plant structures, systems and components (SSC) Examines topics including elimination of ageing effects, plant design, and the application of plant life management (PLiM) practices in a range of commercial nuclear reactor types




Nuclear Reactors


Book Description

Worldwide interest in nuclear reactors continues to increase and significant focus has been placed on advanced nuclear reactors intended to produce electricity and process heat. However, there is limited literature on the importance of research reactors and certain specialized reactor analysis topics. Thus, this book addresses these topics over three sections: “Nuclear Reactors for Spacecraft Propulsion”, “Research Reactors”, and “Select Reactor Analysis Techniques”. It provides detailed information on the use of nuclear reactors for spacecraft propulsion, presents research conducted on reactors in Idaho, USA, and discusses reactor analysis topics such as cyber-informed engineering for nuclear reactor digital instrumentation and control, the effect of plenum gas on fuel temperature, and more.