Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe. Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting.

This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.

Several individuals noted the potentially important civilian uses of atomic energy shortly after the bombings of Hiroshima and Nagasaki in 1945. That year J. Robert Oppenheimer told a national radio audience that "in the near future" it would be possible to generate profitable electric power from "controlled nuclear chain reaction units" (reactors). It was suggested that, after fIfteen to twenty-five years of development, mature nuclear technology could provide virtually inexhaustible, cheap energy given the abundance of nuclear fuel. Admiral Lewis Strauss, the Chairman of the Atomic Energy Commission, stated that atomic power would generate electricity "too cheap to meter" (A statement that, according to Brookhaven National Laboratories' physicist Herbert Kouts, immediately "caused consternation among his technical advisors" [Kouts, 1983: 3)). For a brief period it was thought that airplanes would fly using atomic power, and homes would install small nuclear reactors for heat and hot water. 1950s and early 1960s a small number of prototype nuclear In the reactors came on line in the United States. The first power plant protoype reactor began operation in Shippingport, Pennsylvania in 1957. It was followed by the Dresden 1 unit near Chicago in 1959, the Yankee plant in Rowe, Massachusetts (1960), and the Indian Point (New York) and Big Rock Point (Michigan) plants in 1%2. These five plants had a combined 800 megawatts (800 MW), or less than one generating capacity ofless than percent of the total American electricity generating capacity in 1962.

One of the most critical requirements for safe and reliable nuclear power plant operations is the availability of competent maintenance personnel. However, just as the nuclear power industry is experiencing a renaissance, it is also experiencing an exodus of seasoned maintenance professionals due to retirement. The perfect guide for engineers just entering the field or experienced maintenance supervisors who need to keep abreast of the latest industry best practices, Nuclear Power Plant Maintenance: Mechanical Systems, Equipment and Safety covers the most common issues faced in day-to-day operations and provides practical, technically proven solutions. The book also explains how to navigate the various maintenance codes, standards and regulations for the nuclear power industry. Discusses 50 common issues faced by engineers in the nuclear power plant field Provides advice for complying with international codes and standards (including ASME) Describes safety classification for systems and components Includes case studies to clearly explain the lessons learned over decades in the nuclear power industry

Dynamics and Control of Nuclear Reactors presents the latest knowledge and research in reactor dynamics, control and instrumentation; important factors in ensuring the safe and economic operation of nuclear power plants. This book provides current and future engineers with a single resource containing all relevant information, including detailed treatments on the modeling, simulation, operational features and dynamic characteristics of pressurized light-water reactors, boiling light-water reactors, pressurized heavy-water reactors and molten-salt reactors. It also provides pertinent, but less detailed information on small modular reactors, sodium fast reactors, and gas-cooled reactors. Provides case studies and examples to demonstrate learning through problem solving, including an analysis of accidents at Three Mile Island, Chernobyl and Fukushima Daiichi Includes MATLAB codes to enable the reader to apply the knowledge gained to their own projects and research Features examples and problems that illustrate the principles of dynamic analysis as well as the mathematical tools necessary to understand and apply the analysis Publishers Note: Table 3.1 has been revised and will be included in future printings of the book with the following data: Group Decay Constant, li (sec-1) Delayed Neutron Fraction (bi) 1 0.0124 0.000221 2 0.0305 0.001467 3 0.111 0.001313 4 0.301 0.002647 5 1.14 0.000771 6 3.01 0.000281 Total delayed neutron fraction: 0.0067

Thermal Hydraulics of Water-Cooled Nuclear Reactors reviews flow and heat transfer phenomena in nuclear systems and examines the critical contribution of this analysis to nuclear technology development. With a strong focus on system thermal hydraulics (SYS TH), the book provides a detailed, yet approachable, presentation of current approaches to reactor thermal hydraulic analysis, also considering the importance of this discipline for the design and operation of safe and efficient water-cooled and moderated reactors. Part One presents the background to nuclear thermal hydraulics, starting with a historical perspective, defining key terms, and considering thermal hydraulics requirements in nuclear technology. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. The final part of the book reviews the application of thermal hydraulics in nuclear technology, with chapters on V&V and uncertainty in SYS TH codes, the BEPU approach, and applications to new reactor design, plant lifetime extension, and accident analysis. This book is a valuable resource for academics, graduate students, and professionals studying the thermal hydraulic analysis of nuclear power plants and using SYS TH to demonstrate their safety and acceptability. Contains a systematic and comprehensive review of current approaches to the thermal-hydraulic analysis of water-cooled and moderated nuclear reactors Clearly presents the relationship between system level (top-down analysis) and component level phenomenology (bottom-up analysis) Provides a strong focus on nuclear system thermal hydraulic (SYS TH) codes Presents detailed coverage of the applications of thermal-hydraulics to demonstrate the safety and acceptability of nuclear power plants

Reference for engineers in a wide variety of industries (including power plants and chemical plants) on design of thermal systems.

Dr. Samuel Glasstone, the senior author of the previous editions of this book, was anxious to live until his ninetieth birthday, but passed away in 1986, a few months short of this milestone. I am grateful for the many years of stimulation received during our association, and in preparing this edition have attempted to maintain his approach. Previous editions of this book were intended to serve as a text for students and a reference for practicing engineers. Emphasis was given to the broad perspective, particularly for topics important to reactor design and oper ation, with basic coverage provided in such supporting areas as neutronics, thermal-hydraulics, and materials. This, the Fourth Edition, was prepared with these same general objectives in mind. However, during the past three decades, the nuclear industry and university educational programs have matured considerably, presenting some challenges in meeting the objec tives of this book. Nuclear power reactors have become much more complex, with an ac companying growth in supporting technology. University programs now offer separate courses covering such basic topics as reactor physics, thermal hydraulics, and materials. Finally, the general availability of inexpensive xv xvi Preface powerful micro-and minicomputers has transformed design and analysis procedures so that sophisticated methods are now commonly used instead of earlier, more approximate approaches.

Each number is the catalogue of a specific school or college of the University.

The leading text in the field explains step by step how to writesoftware that responds in real time From power plants to medicine to avionics, the worldincreasingly depends on computer systems that can compute andrespond to various excitations in real time. The Fourth Editionof Real-Time Systems Design and Analysis gives softwaredesigners the knowledge and the tools needed to create real-timesoftware using a holistic, systems-based approach. The text coverscomputer architecture and organization, operating systems, softwareengineering, programming languages, and compiler theory, all fromthe perspective of real-time systems design. The Fourth Edition of this renowned text brings itthoroughly up to date with the latest technological advances andapplications. This fully updated edition includes coverage of thefollowing concepts: Multidisciplinary design challenges Time-triggered architectures Architectural advancements Automatic code generation Peripheral interfacing Life-cycle processes The final chapter of the text offers an expert perspective onthe future of real-time systems and their applications. The text is self-contained, enabling instructors and readers tofocus on the material that is most important to their needs andinterests. Suggestions for additional readings guide readers tomore in-depth discussions on each individual topic. In addition,each chapter features exercises ranging from simple to challengingto help readers progressively build and fine-tune their ability todesign their own real-time software programs. Now fully up to date with the latest technological advances andapplications in the field, Real-Time Systems Design andAnalysis remains the top choice for students and softwareengineers who want to design better and faster real-time systems atminimum cost.

This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

During the last century, nuclear power has been established as a reliable source of energy in the major industrialised countries. It has recently enjoyed a revival in attention and research due to the environmental concerns surrounding current conventional energy sources. Issues of regulation and safety are at the forefront of all discussions involving nuclear power, and will govern its place in the future. The Future of Nuclear Power takes a technical and comprehensive look at the current and future status of nuclear power throughout the world. The 17 chapters are divided into two main sections: a review of all current generation plants, and concepts for new advanced reactor design and safety. The broad-ranging topics covered by this publication, coupled with the current revival of interest in nuclear energy, make it a timely reference for all nuclear scientists. Reviews the issues surrounding the future operation of existing commercial nuclear plants Several chapters dedicated to the extensive research programs in place concerning safe and reliable operation Compares nuclear and non-nuclear options for energy needs in the future; evaluating the benefits and risks of both