Author: Ravindra Munje
Publisher: Springer
ISBN: 9811030146
Category : Technology & Engineering
Languages : en
Pages : 184
Book Description
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.
Investigation of Spatial Control Strategies with Application to Advanced Heavy Water Reactor
Author: Ravindra Munje
Publisher: Springer
ISBN: 9811030146
Category : Technology & Engineering
Languages : en
Pages : 184
Book Description
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.
Publisher: Springer
ISBN: 9811030146
Category : Technology & Engineering
Languages : en
Pages : 184
Book Description
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.
Optimal Control of Distributed Nuclear Reactors
Author: G.S. Christensen
Publisher: Springer Science & Business Media
ISBN: 9780306433054
Category : Mathematics
Languages : en
Pages : 266
Book Description
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.
Publisher: Springer Science & Business Media
ISBN: 9780306433054
Category : Mathematics
Languages : en
Pages : 266
Book Description
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.
Nuclear Science Abstracts
Nuclear Power Reactor Instrumentation Systems Handbook
Author: Joseph M. Harrer
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052
Book Description
Publisher:
ISBN: 9780870790058
Category : Technology & Engineering
Languages : en
Pages : 1052
Book Description
Proceedings of the ... Triennial World Congress of the International Federation of Automatic Control
Author: International Federation of Automatic Control
Publisher:
ISBN:
Category : Automatic control
Languages : en
Pages : 584
Book Description
Publisher:
ISBN:
Category : Automatic control
Languages : en
Pages : 584
Book Description
Pressurized Water Reactors
Author: Yurugi Kanzaki
Publisher: Elsevier
ISBN: 0128235845
Category : Technology & Engineering
Languages : en
Pages : 507
Book Description
Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. - Contains contributions from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience - Includes analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs) - Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe
Publisher: Elsevier
ISBN: 0128235845
Category : Technology & Engineering
Languages : en
Pages : 507
Book Description
Pressurized Water Reactors, Volume Three in the JSME Series on Thermal and Nuclear Power Generation, compiles the latest research on Pressurized Water Reactors (PWRs) into a very comprehensive reference, beginning with its history. The reader is then guided through optimum design processes for PWRs, considering safety throughout. The authors then discuss thermal-hydraulic aspects within the PWR system and inside the reactor core, making this a valuable resource for nuclear and thermal engineers and researchers. Combining their wealth of experience, the book presents in-depth knowledge on the advancement and improvement of fuel rods that is gleaned from decades of experience and lessons learned. The inclusion of analysis codes for the design and safety elements ensure makes this a unique reference which will provide the reader with a solid understanding which they can transfer to their own professional and research settings. Future prospects for next generation PWR and Small Modular Reactors are also discussed, giving the reader a basis for further research of their own. - Contains contributions from the leaders and pioneers in nuclear research at the Japanese Society of Mechanical Engineers and draws upon their combined wealth of knowledge and experience - Includes analysis codes, such as RELAP5, for the design and safety improvement of pressurized water reactors (PWRs) - Presents history, examples, and case studies from Japan and other key regions, such as the United States and Europe
Energy Research Abstracts
Acta Polytechnica Scandinavica
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 646
Book Description
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 646
Book Description
ERDA Energy Research Abstracts
Author: United States. Energy Research and Development Administration. Technical Information Center
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1682
Book Description
Publisher:
ISBN:
Category : Force and energy
Languages : en
Pages : 1682
Book Description