The Technology of Pressurized Water Reactors


Book Description

This book offers a complete panorama of the pressurized water reactor industry, beginning from its origin in the USA and the realization of nuclear engines for naval propulsion, to its most recent developments in the field of civil energy production, particularly in France with the 56 reactors of the multinational electric utility company, Electricité de France (EDF). This comprehensive two-volume masterwork features detailed descriptions of all the crucial components driving a pressurized water nuclear reactor. Volume 1 deals with the main components, such as the main primary circuit, the reactor core, and the steam generators. Volume 2 covers the secondary circuit and the cold source, including components such as the turbine, condenser, alternator, transformers and power supply. Written by Serge Marguet, a leading specialist in reactor physics and author of several books on the subject, this book draws on his experience of more than 35 years in research and development at EDF, a global leader in civil nuclear energy. Featuring a richly illustrated, full-color iconography, as well as a detailed index and bibliography, The Technology of Pressurized Water Reactors is an indispensable work for seasoned nuclear energy professionals, as well as inquisitive newcomers to the field.




Accident Analysis for Nuclear Power Plants


Book Description

Accident analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants (NPPs). The purpose of the report is to provide the necessary practical guidance for performing adequate accident analysis in the light of current good practice worldwide.




Boiling Water Reactor Plant


Book Description




Nuclear Reactor Kinetics and Plant Control


Book Description

Understanding time-dependent behaviors of nuclear reactors and the methods of their control is essential to the operation and safety of nuclear power plants. This book provides graduate students, researchers, and engineers in nuclear engineering comprehensive information on both the fundamental theory of nuclear reactor kinetics and control and the state-of-the-art practice in actual plants, as well as the idea of how to bridge the two. The first part focuses on understanding fundamental nuclear kinetics. It introduces delayed neutrons, fission chain reactions, point kinetics theory, reactivity feedbacks, and related measurement techniques. The second part helps readers to grasp the theories and practice of nuclear power plant control. It introduces control theory, nuclear reactor stability, and the operation and control of existing nuclear power plants such as a typical pressurized water reactor, a typical boiling water reactor, the prototype fast breeder reactor Monju, and the high-temperature gas-cooled test reactor (HTTR). Wherever possible, the design and operation data for these plants are provided.




The Physics of Nuclear Reactors


Book Description

This comprehensive volume offers readers a progressive and highly detailed introduction to the complex behavior of neutrons in general, and in the context of nuclear power generation. A compendium and handbook for nuclear engineers, a source of teaching material for academic lecturers as well as a graduate text for advanced students and other non-experts wishing to enter this field, it is based on the author’s teaching and research experience and his recognized expertise in nuclear safety. After recapping a number of points in nuclear physics, placing the theoretical notions in their historical context, the book successively reveals the latest quantitative theories concerning: • The slowing-down of neutrons in matter • The charged particles and electromagnetic rays • The calculation scheme, especially the simplification hypothesis • The concept of criticality based on chain reactions • The theory of homogeneous and heterogeneous reactors • The problem of self-shielding • The theory of the nuclear reflector, a subject largely ignored in literature • The computational methods in transport and diffusion theories Complemented by more than 400 bibliographical references, some of which are commented and annotated, and augmented by an appendix on the history of reactor physics at EDF (Electricité De France), this book is the most comprehensive and up-to-date introduction to and reference resource in neutronics and reactor theory.




Dynamics and Control of Nuclear Reactors


Book Description

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




Super Light Water Reactors and Super Fast Reactors


Book Description

Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.




Pressurized Heavy Water Reactors


Book Description

Pressurized Heavy Water Reactors: CANDU, the seventh volume in the JSME Series on Thermal and Nuclear Power Generation series, provides a comprehensive and complete review of a single type of reactor in a very accessible and practical way. The book presents the full lifecycle, from design and manufacturing to operation and maintenance, also covering fitness-for-service and long-term operation. It 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, the book offers practical solutions to common problems faced, along with the safe and approved processes to reach suitable solutions. Professionals involved in nuclear power plant lifecycle 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. Provides 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 lifecycle, from design, manufacturing, operation, maintenance and long-term operation







The Shippingport Pressurized Water Reactor


Book Description

A total of 193 annotated references to unclassified reports on the design, development and construction of the Shippingport Pressurized Water Reactor is presented. Author, subject, and report number indexes are included.