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Book Modeling and Control of a Large Nuclear Reactor

Download or read book Modeling and Control of a Large Nuclear Reactor written by S R Shimjith and published by Springer. This book was released on 2012-08-10 with total page 154 pages. Available in PDF, EPUB and Kindle. Book excerpt: Control analysis and design of large nuclear reactors requires a suitable mathematical model representing the steady state and dynamic behavior of the reactor with reasonable accuracy. This task is, however, quite challenging because of several complex dynamic phenomena existing in a reactor. Quite often, the models developed would be of prohibitively large order, non-linear and of complex structure not readily amenable for control studies. Moreover, the existence of simultaneously occurring dynamic variations at different speeds makes the mathematical model susceptible to numerical ill-conditioning, inhibiting direct application of standard control techniques. This monograph introduces a technique for mathematical modeling of large nuclear reactors in the framework of multi-point kinetics, to obtain a comparatively smaller order model in standard state space form thus overcoming these difficulties. It further brings in innovative methods for controller design for systems exhibiting multi-time-scale property, with emphasis on three-time-scale systems.

Book Dynamics and Control of Nuclear Reactors

Download or read book Dynamics and Control of Nuclear Reactors written by Thomas W. Kerlin and published by Academic Press. This book was released on 2019-10-05 with total page 402 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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

Book Optimal Control of Distributed Nuclear Reactors

Download or read book Optimal Control of Distributed Nuclear Reactors written by G.S. Christensen and published by Springer Science & Business Media. This book was released on 2013-11-11 with total page 246 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is devoted to the mathematical optimization theory and modeling techniques that recently have been applied to the problem of controlling the shape and intensity of the power density distribution in the core of large nuclear reactors. The book has been prepared with the following purposes in mind: 1. To provide, in a condensed manner, the background preparation on reactor kinetics required for a comprehensive description of the main problems encountered in designing spatial control systems for nuclear reactor cores. 2. To present the work that has already been done on this subject and provide the basic mathematical tools required for a full understand ing of the different methods proposed in the literature. 3. To stimulate further work in this challenging area by weighting the advantages and disadvantages of the existing techniques and evaluating their effectiveness and applicability. In addition to coverage of the standard topics on the subject of optimal control for distributed parametersystems, the book includes, at amathemati cal level suitable for graduate students in engineering, discussions of con ceptsoffunctional analysis, the representation theory ofgroups, and integral equations. Although these topics constitute a requisite for a full understanding of the new developments in the area of reactor modeling and control, they are seidom treated together in a single book and, when they are, their presenta tion isoften directed to the mathematician.They are thus relatively unknown to the engineering community.

Book Fractional order Modeling of Nuclear Reactor  From Subdiffusive Neutron Transport to Control oriented Models

Download or read book Fractional order Modeling of Nuclear Reactor From Subdiffusive Neutron Transport to Control oriented Models written by Vishwesh Vyawahare and published by Springer. This book was released on 2018-02-03 with total page 210 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book addresses the topic of fractional-order modeling of nuclear reactors. Approaching neutron transport in the reactor core as anomalous diffusion, specifically subdiffusion, it starts with the development of fractional-order neutron telegraph equations. Using a systematic approach, the book then examines the development and analysis of various fractional-order models representing nuclear reactor dynamics, ultimately leading to the fractional-order linear and nonlinear control-oriented models. The book utilizes the mathematical tool of fractional calculus, the calculus of derivatives and integrals with arbitrary non-integer orders (real or complex), which has recently been found to provide a more compact and realistic representation to the dynamics of diverse physical systems. Including extensive simulation results and discussing important issues related to the fractional-order modeling of nuclear reactors, the book offers a valuable resource for students and researchers working in the areas of fractional-order modeling and control and nuclear reactor modeling.

Book A New Model Concept for Large Nuclear Reactors

Download or read book A New Model Concept for Large Nuclear Reactors written by R. A. Harvey and published by . This book was released on 1964 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Modeling for the Simulation and Control of Nuclear Reactor Rocket Systems

Download or read book Modeling for the Simulation and Control of Nuclear Reactor Rocket Systems written by Jonathan Keay Witter and published by . This book was released on 1993 with total page 536 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor

Download or read book Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor written by Ravindra Munje and published by Springer. This book was released on 2017-10-13 with total page 184 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book examines the different spatial control techniques for regulation of spatial power distribution in advanced heavy water reactors (AHWR). It begins with a review of the literature pertinent to the modeling and control of large reactors. It also offers a nodal-core model based on finite difference approximation since the AHWR core is considered to be divided into 17 relatively large nodes. Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR. The book also presents a vectorized nonlinear model of AHWR and implements it in MATLAB/Simulink environment. The model of the reactor is then linearized at the rated power and put into standard state variable form. It is characterized by 90 states, 5 inputs and 18 outputs. Lastly, it discusses control techniques for a nonlinear model of AHWR. This book will prove to be a valuable resource for professional engineers and implementation specialists, researchers and students.

Book Simulation and Control of a Nuclear Reactor

Download or read book Simulation and Control of a Nuclear Reactor written by Kenneth I. Hunter and published by . This book was released on 1974 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Model based control of a research nuclear reactor  MS

Download or read book Model based control of a research nuclear reactor MS written by Xiao Xu and published by . This book was released on 1994 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Structural Materials for Generation IV Nuclear Reactors

Download or read book Structural Materials for Generation IV Nuclear Reactors written by Pascal Yvon and published by Woodhead Publishing. This book was released on 2016-08-27 with total page 686 pages. Available in PDF, EPUB and Kindle. Book excerpt: Operating at a high level of fuel efficiency, safety, proliferation-resistance, sustainability and cost, generation IV nuclear reactors promise enhanced features to an energy resource which is already seen as an outstanding source of reliable base load power. The performance and reliability of materials when subjected to the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors are essential areas of study, as key considerations for the successful development of generation IV reactors are suitable structural materials for both in-core and out-of-core applications. Structural Materials for Generation IV Nuclear Reactors explores the current state-of-the art in these areas. Part One reviews the materials, requirements and challenges in generation IV systems. Part Two presents the core materials with chapters on irradiation resistant austenitic steels, ODS/FM steels and refractory metals amongst others. Part Three looks at out-of-core materials. Structural Materials for Generation IV Nuclear Reactors is an essential reference text for professional scientists, engineers and postgraduate researchers involved in the development of generation IV nuclear reactors. - Introduces the higher neutron doses and extremely corrosive higher temperature environments that will be found in generation IV nuclear reactors and implications for structural materials - Contains chapters on the key core and out-of-core materials, from steels to advanced micro-laminates - Written by an expert in that particular area

Book Multi modular Nuclear Reactor Plant Simulation and Control

Download or read book Multi modular Nuclear Reactor Plant Simulation and Control written by Mather Knight Waltrip and published by . This book was released on 1989 with total page 360 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Physics of Nuclear Reactors

Download or read book The Physics of Nuclear Reactors written by Serge Marguet and published by Springer. This book was released on 2018-02-26 with total page 1462 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Book Baseline Assessment of TREAT for Modeling and Analysis Needs

Download or read book Baseline Assessment of TREAT for Modeling and Analysis Needs written by and published by . This book was released on 2015 with total page 347 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Transient Reactor Test Facility (TREAT) is an air-cooled, thermal, heterogeneous test facility designed to evaluate reactor fuels and structural materials under conditions simulating various types of nuclear excursions and transient undercooling situations the could occur in a nuclear reactor. Fuel meltdowns, metal-water reactions, thermal interaction between overheated fuel and coolant, and the transient behavior of ceramic fuel for high temperature systems can be investigated [Freund 1958]. The contribution by TREAT to reactor safety includes the following: 1) provision of basic data to predict the safety margin of fuel designs and the severity of potential accidents, 2) service as a proving ground for fuel concepts designed to reduce or prevent consequent hazards, and 3) provision of nondestructive test data via neutron radiography of fuel samples irradiated in other test reactors [Sachs 1974]. The major unique features of TREAT include large flux integral absorption due to its high heat capacity; inherent, essentially instantaneous, temperature-dependent shutdown mechanism; rapid control rod movement; and visual access to the core center [MacFarlane 1958]. TREAT's primary purpose was to simulate accident conditions leading to fuel damge, including melting or vaporization of the test specimens, while leaving undamaged the reactor's fuel. During steady-state operation, TREAT could be utilized as a large neutron-radiography facility and could examine assemblies up to 15 ft. in length. Unique shielded viewing slots allowed for both optical and gamma camera systems to record reactive mechanisms occurring during the experiment on film for detailed study. A fast-neutron hodoscope was a key diagnostic instrument that by collimating and detecting fission neutrons emitted by experiment fuel samples could provide time and spatial resolution of fuel motion during transients and in-place measurement of fuel distribution before and after an experiment. The reactor was operated from February 1959 until April 1994, generating over 720 MWh of energy. The reactor underwent a major upgrade in 1988, which included installation of new instrumentation and control systems, with refurbishment of the rod drive systems. The only major difference, in-core, between the preupgrade core and the upgraded core was the change in the number and locations of the control rods; all other neutronics behavior is essentially unchanged.

Book NUREG CR

    Book Details:
  • Author : U.S. Nuclear Regulatory Commission
  • Publisher :
  • Release : 1977
  • ISBN :
  • Pages : 48 pages

Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1977 with total page 48 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Introductory Nuclear Reactor Dynamics

Download or read book Introductory Nuclear Reactor Dynamics written by Karl Otto Ott and published by . This book was released on 1985 with total page 384 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text presents the theory and methods of prediction that are the heart of nuclear reactor safety. Time-dependent reactor behavior is explained in both mathematical and physical terms. This book also explains the logic behind the working formulas and calculational methods for reactor transients and illustrates typical dynamic responses. The classical concept of point kinetics is developed in three steps, with discussion of various solutions to kinetics problems. Each chapter includes homework problems and review questions.

Book Nuclear Power

    Book Details:
  • Author : National Research Council
  • Publisher : National Academies Press
  • Release : 1992-02-01
  • ISBN : 0309043956
  • Pages : 234 pages

Download or read book Nuclear Power written by National Research Council and published by National Academies Press. This book was released on 1992-02-01 with total page 234 pages. Available in PDF, EPUB and Kindle. Book excerpt: The construction of nuclear power plants in the United States is stopping, as regulators, reactor manufacturers, and operators sort out a host of technical and institutional problems. This volume summarizes the status of nuclear power, analyzes the obstacles to resumption of construction of nuclear plants, and describes and evaluates the technological alternatives for safer, more economical reactors. Topics covered include: Institutional issues-including regulatory practices at the federal and state levels, the growing trends toward greater competition in the generation of electricity, and nuclear and nonnuclear generation options. Critical evaluation of advanced reactors-covering attributes such as cost, construction time, safety, development status, and fuel cycles. Finally, three alternative federal research and development programs are presented.

Book Nuclear Reactor Analysis

Download or read book Nuclear Reactor Analysis written by James J. Duderstadt and published by Wiley. This book was released on 1991-01-16 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: Classic textbook for an introductory course in nuclear reactor analysis that introduces the nuclear engineering student to the basic scientific principles of nuclear fission chain reactions and lays a foundation for the subsequent application of these principles to the nuclear design and analysis of reactor cores. This text introduces the student to the fundamental principles governing nuclear fission chain reactions in a manner that renders the transition to practical nuclear reactor design methods most natural. The authors stress throughout the very close interplay between the nuclear analysis of a reactor core and those nonnuclear aspects of core analysis, such as thermal-hydraulics or materials studies, which play a major role in determining a reactor design.