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Book Digital Computers and Nuclear Reactor Calculations

Download or read book Digital Computers and Nuclear Reactor Calculations written by Ward Conrad Sangren and published by . This book was released on 1960 with total page 230 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Reactor Calculations with the Group Diffusion Equations on Digital Computers

Download or read book Nuclear Reactor Calculations with the Group Diffusion Equations on Digital Computers written by Willem Jacobus van de Lindt and published by . This book was released on 1964 with total page 140 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Digital Computers and Nuclear Reactor Calculation

Download or read book Digital Computers and Nuclear Reactor Calculation written by Ward Conrad Sangren and published by . This book was released on 1960 with total page 208 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Digital Computers and Nuclear Design

Download or read book Digital Computers and Nuclear Design written by D. S. Selengut and published by . This book was released on 1959 with total page 58 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Reactor Simulation by Analog Computer a Literature Survey

Download or read book Nuclear Reactor Simulation by Analog Computer a Literature Survey written by R. J. Allen and published by . This book was released on 1959 with total page 70 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Application of On line Computers to Nuclear Reactors

Download or read book Application of On line Computers to Nuclear Reactors written by European Nuclear Energy Agency and published by . This book was released on 1969 with total page 922 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Nuclear Reactor Kinetics and Control

Download or read book Nuclear Reactor Kinetics and Control written by Jeffery Lewins and published by Elsevier. This book was released on 2013-10-22 with total page 282 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear Reactor Kinetics and Control highlights the application of classical control methods in the frequency space to the dynamic processes of a nuclear reactor. This book contains nine chapters and begins with an introduction to some important mathematical theories related to nuclear engineering, such as the Laplace and Fourier transforms, linear system stability, and the probability theory. The succeeding chapters deal with the frequency space of classical linear design. A chapter describes a stochastic model for the “lumped reactor and presents equations that measure the departure from the mean, as well as representative experiments or applications of the theory to neutron detection. The discussion then shifts to the aspects of reliability and its consequences for safety of nuclear reactors and some techniques for nonlinear studies centered on the use of the state space and its equations in the time domain. The final chapter introduces the modern electric analogue computer and derives the patching or programming rules that can be use to find solutions to problems of interest using the analogous behavior of electric circuits. This chapter also provide examples of intrinsic interest in nuclear engineering showing the programming involved and typical results, including the slower transients of xenon poisoning and fuel burn-up. This book is intended for nuclear engineers, physicists, applied mathematicians, and nuclear engineering undergraduate and postgraduate students.

Book An Introduction to the Neutron Kinetics of Nuclear Power Reactors

Download or read book An Introduction to the Neutron Kinetics of Nuclear Power Reactors written by J. G. Tyror and published by Elsevier. This book was released on 2013-10-22 with total page 194 pages. Available in PDF, EPUB and Kindle. Book excerpt: An Introduction to the Neutron Kinetics of Nuclear Power Reactors introduces the reader to the neutron kinetics of nuclear power reactors. Topics covered include the neutron physics of reactor kinetics, feedback effects, water-moderated reactors, fast reactors, and methods of plant control. The reactor transients following faults are also discussed, along with the use of computers in the study of power reactor kinetics. This book is comprised of eight chapters and begins with an overview of the reactor physics characteristics of a nuclear power reactor and their influence on system design and operation. The use of a mathematical model of the system to study reactor kinetics and control is described. The following chapters explore the neutronic aspects of reactor kinetics; the interaction between neutronic events and the behavior of other physical quantities of the reactor; the influence of feedback effects on neutron kinetics; and the neutron kinetics of water-moderated reactors and fast reactors. The different control schemes for nuclear power reactors are also considered. The final chapter looks at the use of computers to solve the equations of kinetic models for nuclear power reactors. This monograph will be a useful resource for nuclear scientists, physicists, and engineers.

Book Advances in Nuclear Science and Technology

Download or read book Advances in Nuclear Science and Technology written by Ernest J. Henley and published by Academic Press. This book was released on 2014-05-12 with total page 389 pages. Available in PDF, EPUB and Kindle. Book excerpt: Advances in Nuclear Science and Technology, Volume 2 provides an authoritative, complete, coherent, and critical review of the nuclear industry. This book discusses the advances in the atomic energy field. Organized into six chapters, this volume begins with an overview of the concept of transfer function of a system. This text then examines the classic plant cycles for the water-cooled, liquid metal, and gas-cooled reactor concepts to pinpoint those points in cycle that require nuclear grade heat exchanger equipment. Other chapters consider heat exchanger, which is applied to the full spectrum of apparatus and equipment designed to facilitate the flow of heat from medium to medium. This book discusses as well the hardware characteristics and the resulting effects on reactor calculations. The final chapter deals with the effect of digital computers on nuclear reactor calculations and discusses some of the numerical methods used in nuclear reactor codes. This book is a valuable resource for design engineers and plant operating personnel.

Book Summary of the GE ANP Reactor Machine Computation Program

Download or read book Summary of the GE ANP Reactor Machine Computation Program written by D. S. Selengut and published by . This book was released on 1955 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Guide to the Application of Digital Computers to Nuclear Reactor Instrumentation and Control

Download or read book Guide to the Application of Digital Computers to Nuclear Reactor Instrumentation and Control written by British Standards Institute Staff and published by . This book was released on 1981-10-30 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Nuclear reactors, Nuclear technology, Instruments, Computer applications, Process control, Control equipment, Digital computers, Reliability, Alarm systems, Instrumentation recording, Control systems, Grades (quality), Display devices, Computerized control

Book Modelling of Nuclear Reactor Multi physics

Download or read book Modelling of Nuclear Reactor Multi physics written by Christophe Demazière and published by Academic Press. This book was released on 2019-11-19 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).The first chapter introduces the book’s subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference Analyses the emerging area of multi-physics and multi-scale reactor modelling Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding