A Review of the Discrete Ordinates Sn Method for Radiation Transport Calculations

A Review of the Discrete Ordinates Sn Method for Radiation Transport Calculations PDF Author: Radiation Shielding Information Center (U.S.) Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Boltzmann equation
Languages : en
Pages : 240

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A Review of the Discrete Ordinates Sn Method for Radiation Transport Calculations

A Review of the Discrete Ordinates Sn Method for Radiation Transport Calculations PDF Author: Radiation Shielding Information Center (U.S.) Oak Ridge National Laboratory
Publisher:
ISBN:
Category : Boltzmann equation
Languages : en
Pages : 240

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Nuclear Science Abstracts

Nuclear Science Abstracts PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 978

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Neutron Dosimetry in Radiation Protection

Neutron Dosimetry in Radiation Protection PDF Author: H. Ing
Publisher:
ISBN:
Category : Neutrons
Languages : en
Pages : 368

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The Physics of Nuclear Reactors

The Physics of Nuclear Reactors PDF Author: Serge Marguet
Publisher: Springer
ISBN: 3319595601
Category : Science
Languages : en
Pages : 1462

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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.

Transactions of the American Nuclear Society

Transactions of the American Nuclear Society PDF Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 838

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Computational Methods in Transport

Computational Methods in Transport PDF Author: Frank Graziani
Publisher: Springer Science & Business Media
ISBN: 3540281258
Category : Computers
Languages : en
Pages : 539

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Thereexistawiderangeofapplicationswhereasigni?cantfractionofthe- mentum and energy present in a physical problem is carried by the transport of particles. Depending on the speci?capplication, the particles involved may be photons, neutrons, neutrinos, or charged particles. Regardless of which phenomena is being described, at the heart of each application is the fact that a Boltzmann like transport equation has to be solved. The complexity, and hence expense, involved in solving the transport problem can be understood by realizing that the general solution to the 3D Boltzmann transport equation is in fact really seven dimensional: 3 spatial coordinates, 2 angles, 1 time, and 1 for speed or energy. Low-order appro- mations to the transport equation are frequently used due in part to physical justi?cation but many in cases, simply because a solution to the full tra- port problem is too computationally expensive. An example is the di?usion equation, which e?ectively drops the two angles in phase space by assuming that a linear representation in angle is adequate. Another approximation is the grey approximation, which drops the energy variable by averaging over it. If the grey approximation is applied to the di?usion equation, the expense of solving what amounts to the simplest possible description of transport is roughly equal to the cost of implicit computational ?uid dynamics. It is clear therefore, that for those application areas needing some form of transport, fast, accurate and robust transport algorithms can lead to an increase in overall code performance and a decrease in time to solution.

Nuclear Computational Science

Nuclear Computational Science PDF Author: Yousry Azmy
Publisher: Springer Science & Business Media
ISBN: 9048134110
Category : Technology & Engineering
Languages : en
Pages : 476

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Nuclear engineering has undergone extensive progress over the years. In the past century, colossal developments have been made and with specific reference to the mathematical theory and computational science underlying this discipline, advances in areas such as high-order discretization methods, Krylov Methods and Iteration Acceleration have steadily grown. Nuclear Computational Science: A Century in Review addresses these topics and many more; topics which hold special ties to the first half of the century, and topics focused around the unique combination of nuclear engineering, computational science and mathematical theory. Comprising eight chapters, Nuclear Computational Science: A Century in Review incorporates a number of carefully selected issues representing a variety of problems, providing the reader with a wealth of information in both a clear and concise manner. The comprehensive nature of the coverage and the stature of the contributing authors combine to make this a unique landmark publication. Targeting the medium to advanced level academic, this book will appeal to researchers and students with an interest in the progression of mathematical theory and its application to nuclear computational science.

Computer Techniques in Radiation Transport and Dosimetry

Computer Techniques in Radiation Transport and Dosimetry PDF Author: Walter R. Nelson
Publisher: Springer Science & Business Media
ISBN: 1468436082
Category : Science
Languages : en
Pages : 513

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Book Description
In October 1978, a group of 41 scientists from 14 countries met in Erice, Sicily to attend the Second Course of the Interna tional School of Radiation Damage and Protection "Ettore Majorana", the proceedings of which are contained in this book. The countries represented at the School were: Brazil, Canada, Federal Republic of Germany, Finland, German Democratic Republic, Hungary, India, Italy, Japan, Spain, Sweden, Switzerland, United States of America, and Yugoslavia. The School was officially sponsored by the Italian Health Physics Association, the Italian Ministry of Public Education, the Italian Ministry of Scientific and Technological Research, and the Sicilian Regional Government. In addition, administrative and tech nical support was received from the Stanford Linear Accelerator Center and from CERN. The past 15 or so years have witnessed a significant develop ment of computer methods in the science of radiation protection. The radiation transport codes associated with hadronic and electro magnetic cascades, reactor shielding, unfolding techniques, and gamma ray spectrum analysis have reached the state-of-the-art level, and the Erice Course aimed at presenting as comprehensive an over view of these programs as was possible within the allotted time span.

Advances in Dosimetry for Fast Neutrons and Heavy Charged Particles for Therapy Applications

Advances in Dosimetry for Fast Neutrons and Heavy Charged Particles for Therapy Applications PDF Author: International Atomic Energy Agency
Publisher:
ISBN:
Category : Business & Economics
Languages : en
Pages : 318

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Scientific and Technical Aerospace Reports

Scientific and Technical Aerospace Reports PDF Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 364

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