Pressurized Heavy Water Reactors: Atucha-2 is the eighth volume in the JSME Series on Thermal and Nuclear Power Generation. Edited by Jovica Riznic, this volume is the fifth to provide a comprehensive and complete review of a single type of reactor in a very accessible and practical way. This volume presents a close analysis of the Atucha reactor, covering reactor physics, aging management of major components and the role of codes in PHWR and Nuclear Regulation and Licensing, before providing a detailed description of Atucha-2 Plant design. Including contemporary capabilities and challenges of nuclear technology, this book offers solutions and advice on common problems faced and guides the reader through safe and approved processes to reach suitable solutions. Professionals involved in life-cycle assessment of the Atucha plant, and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, design and licensing. A comprehensive reference on the latest research on Atucha Pressurized Heavy Water Reactors and their impact on sustainability goals Analyses The Atucha-2 BEPU and LBLOCA Considers the licensing of Atucha-2, its physics and aging management of major components
Pressurized Heavy Water Reactors: CANDU is the seventh volume in the JSME Series on Thermal and Nuclear Power Generation. Edited by Jovica Riznic, this volume is the fourth to provide a comprehensive and complete review of a single type of reactor in a very accessible and practical way. This volume presents the full life-cycle from design and manufacturing, through to operation and maintenance, and also covers fitness-for-service and long-term operation. This book does not relate to any specific vendor-based technology, but rather provides a broad overview of the latest technologies from a variety of active locations which will be of great value to countries invested in developing their own nuclear programs. Including contemporary capabilities and challenges of nuclear technology, this book offers practical solutions to common problems faced, and guides the reader through safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant life-cycle assessment and researchers interested in the development and improvement of nuclear energy technologies will gain a deep understanding of PHWR nuclear reactor physics, chemistry and thermal-hydraulic properties. A complete reference dedicated to the latest research on Pressurized Heavy Water Reactors and their economic and environmental benefits Goes beyond CANDU reactors to analyze the popular German and Indian designs, as well as plant design in Korea, Romania, China and Argentina Spans all phases of the nuclear power plant life-cycle, from design, manufacturing, operation and maintenance, through to long-term operation
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
|Author||: Russian Academy of Sciences,National Research Council,Policy and Global Affairs,Development, Security, and Cooperation,Office for Central Europe and Eurasia,Committee on the Scientific Aspects of an International Spent Nuclear Fuel Storage Facility in Russia|
|Publisher||: National Academies Press|
|Release Date||: 2005-10-03|
|ISBN 10||: 9780309181181|
|Pages||: 302 pages|
As part of a long-standing collaboration on nuclear nonproliferation, the National Academy of Sciences and the Russian Academy of Sciences held a joint workshop in Moscow in 2003 on the scientific aspects of an international radioactive disposal site in Russia. The passage of Russian laws permitting the importation and storage of high-level radioactive material (primarily spent nuclear fuel from reactors) has engendered interest from a number of foreign governments, including the U.S., in exploring the possibility of transferring material to Russia on a temporary or permanent basis. The workshop focused on the environmental aspects of the general location and characteristics of a possible storage site, transportation to and within the site, containers for transportation and storage, inventory and accountability, audits and inspections, and handling technologies.
|Release Date||: 1977|
|Pages||: 329 pages|
ERDA has requested United Engineers and Constructors (UE and C) to evaluate the design of the Canadian natural uranium fueled, heavy water moderated (CANDU) nuclear reactor power plant to assess its conformance with the licensing criteria and guidelines of the U.S. Nuclear Regulatory Commission (USNRC) for light water reactors. This assessment was used to identify cost significant items of nonconformance and to provide a basis for developing a detailed cost estimate for a 1140 MWe, 3-loop Pressurized Heavy Water Reactor (PHWR) located at the Middletown, USA Site.
Nuclear Energy Materials and Reactors is a component of Encyclopedia of Energy Sciences, Engineering and Technology Resources in the global Encyclopedia of Life Support Systems (EOLSS), which is an integrated compendium of twenty one Encyclopedias. Nuclear energy is a type of technology involving the controlled use of nuclear fission to release energy for work including propulsion, heat, and the generation of electricity. The theme on Nuclear Energy Materials and Reactors discusses: Fundamentals of Nuclear Energy; Nuclear Physics; Nuclear Interactions; Nuclear Reactor Theory; Nuclear Reactor Design; Nuclear Reactor Kinetics; Reactivity Changes; Nuclear Power Plants; Pressurized Water Reactors; Boiling Water Reactors; Pressurized Heavy Water Reactors; Heavy Water Light Water Reactors; Advanced Gas Cooled Reactors; Light Water Graphite Reactors; High Temperature Gas Cooled Reactors; Pebble Bed Modular Reactor; Radioactive Wastes, Origins, Classification and Management; Nuclear Reactor Overview and Reactor Cycles; The Nuclear Reactor Closed Cycle; Safety of Boiling Water Reactors; Supercritical Water-Cooled Nuclear Reactors: Review and Status; The Gas-Turbine Modular Helium Reactor; Application of Risk Assessment to Nuclear Power Plants; Production and Recycling Resources for Nuclear Fission. These two volumes are aimed at the following five major target audiences: University and College students Educators, Professional practitioners, Research personnel and Policy analysts, managers, and decision makers.
Steam Generators for Nuclear Power Plants examines all phases of the lifecycle of nuclear steam generators (NSGs), components which are essential for the efficient and safe operation of light water reactors (LWRs). Coverage spans the design, manufacturing, operation and maintenance, fitness-for-service, and long-term operation of these key reactor parts. Part One opens with a chapter that provides fundamental background on NSG engineering and operational experiences. Following chapters review the different NSG concepts, describe NSG design and manufacturing, and consider the particularities of SGs for VVER reactors. Part Two focuses on NSG operation and maintenance, starting with an overview of the activities required to support reliable and safe operation. The discussion then moves on to tubing vibration, followed by the water and steam cycle chemistry issues relevant to the NSG lifecycle. Finally, a number of chapters focus on the key issue of corrosion in NSGs from different angles. This book serves as a timely resource for professionals involved in all phases of the NSG lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation. It is also intended as a valuable resource for students and researchers interested in a range of topics relating to NSG lifecycle management. Fulfills the need for a detailed reference on steam generators for nuclear power plants Contains comprehensive coverage of all phases of the nuclear steam generator lifecycle, from design, manufacturing, operation and maintenance, to fitness-for-service and long-term operation in one convenient volume Presents contributions from key manufacturers and research institutes and universities
This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents, in order to teach nuclear professionals how to mitigate potential risks to the public to the maximum extent possible. Engineers, researchers, students and the personnel of vendors, safety authorities and nuclear power generation organizations require the knowledge offered by this volume's globally renowned experts to ensure they obtain a core competency in nuclear safety. Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information Explains how developments in the field of LWR severe accidents have provided more accurate determinations of risk, thereby shedding new light on the debates surrounding nuclear power safety, particularly in light of the recent tragedy in Japan Concentrates on prevention and management of accidents, developing methodologies to estimate the consequences and associated risks
Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches
This book is intended to provide an introduction to the basic principles of nuclear fission reactors for advanced undergraduate or graduate students of physics and engineering. The presentation is also suitable for physicists or engineers who are entering the nuclear power field without previous experience with nuclear reactors. No background knowledge is required beyond that typically acquired in the first two years of an undergraduate program in physics or engineering. Throughout, the emphasis is on explaining why particular reactor systems have evolved in the way they have, without going into great detail about reactor physics or methods of design analysis, which are already covered in a number of excellent specialist texts. The first two chapters serve as an introduction to the basic physics of the atom and the nucleus and to nuclear fission and the nuclear chain reaction. Chapter 3 deals with the fundamentals of nuclear reactor theory, covering neutron slowing down and the spatial dependence of the neutron flux in the reactor, based on the solution of the diffusion equations. The chapter includes a major section on reactor kinetics and control, including'tempera ture and void coefficients and xenon poisoning effects in power reactors. Chapter 4 describes various aspects offuel management and fuel cycles, while Chapter 5 considers materials problems for fuel and other constituents of the reactor. The processes of heat generation and removal are covered in Chapter 6.