Author: David L. Monti
Publisher:
ISBN:
Category :
Languages : en
Pages : 138
Book Description
The Monte Carlo transport code, MCNP was modified for purposes of two dimensional neutron-photon transport modelling in a variable density atmosphere. Calculations were performed using cylindrical (r, z) geometry and a point isotropic neutron-photon source at an elevation of 40 kilometers. Neutron and photon fluence results were computed using ring detectors for field points at constant range versus source elevation angle and for field points at constant altitude versus radius. Comparisons between the modified and unmodified versions of MCNP showed a decrease in run time by a factor of two was possible. Only a fraction of the spatial cells previously required were used. Results showed streaming of the neutron and photon radiation at very close ranges. Buildup from multiple scattering contributions proved to be the dominant effect at intermediate ranges. Attenuation from successive downscatter in energy was shown to be the dominant effect at ranges greater than about 60 kilometers. Results obtained with MCNP were compared to those obtained with the computer code SMAUG- II, which uses the mass-integral scaling approximation. The comparison showed SMAUG-II to be accurate at points close to the source, but serious errors were encountered at ranges exceeding 9 kilometers as the mass range increased.
High Altitude Neutral Particle Transport Using the Monte Carlo Simulation Code MCNP with Variable Density Atmosphere
Author: David L. Monti
Publisher:
ISBN:
Category :
Languages : en
Pages : 138
Book Description
The Monte Carlo transport code, MCNP was modified for purposes of two dimensional neutron-photon transport modelling in a variable density atmosphere. Calculations were performed using cylindrical (r, z) geometry and a point isotropic neutron-photon source at an elevation of 40 kilometers. Neutron and photon fluence results were computed using ring detectors for field points at constant range versus source elevation angle and for field points at constant altitude versus radius. Comparisons between the modified and unmodified versions of MCNP showed a decrease in run time by a factor of two was possible. Only a fraction of the spatial cells previously required were used. Results showed streaming of the neutron and photon radiation at very close ranges. Buildup from multiple scattering contributions proved to be the dominant effect at intermediate ranges. Attenuation from successive downscatter in energy was shown to be the dominant effect at ranges greater than about 60 kilometers. Results obtained with MCNP were compared to those obtained with the computer code SMAUG- II, which uses the mass-integral scaling approximation. The comparison showed SMAUG-II to be accurate at points close to the source, but serious errors were encountered at ranges exceeding 9 kilometers as the mass range increased.
Publisher:
ISBN:
Category :
Languages : en
Pages : 138
Book Description
The Monte Carlo transport code, MCNP was modified for purposes of two dimensional neutron-photon transport modelling in a variable density atmosphere. Calculations were performed using cylindrical (r, z) geometry and a point isotropic neutron-photon source at an elevation of 40 kilometers. Neutron and photon fluence results were computed using ring detectors for field points at constant range versus source elevation angle and for field points at constant altitude versus radius. Comparisons between the modified and unmodified versions of MCNP showed a decrease in run time by a factor of two was possible. Only a fraction of the spatial cells previously required were used. Results showed streaming of the neutron and photon radiation at very close ranges. Buildup from multiple scattering contributions proved to be the dominant effect at intermediate ranges. Attenuation from successive downscatter in energy was shown to be the dominant effect at ranges greater than about 60 kilometers. Results obtained with MCNP were compared to those obtained with the computer code SMAUG- II, which uses the mass-integral scaling approximation. The comparison showed SMAUG-II to be accurate at points close to the source, but serious errors were encountered at ranges exceeding 9 kilometers as the mass range increased.
Monte Carlo Methods for Particle Transport
Author: Alireza Haghighat
Publisher: CRC Press
ISBN: 042958220X
Category : Mathematics
Languages : en
Pages : 214
Book Description
Fully updated with the latest developments in the eigenvalue Monte Carlo calculations and automatic variance reduction techniques and containing an entirely new chapter on fission matrix and alternative hybrid techniques. This second edition explores the uses of the Monte Carlo method for real-world applications, explaining its concepts and limitations. Featuring illustrative examples, mathematical derivations, computer algorithms, and homework problems, it is an ideal textbook and practical guide for nuclear engineers and scientists looking into the applications of the Monte Carlo method, in addition to students in physics and engineering, and those engaged in the advancement of the Monte Carlo methods. Describes general and particle-transport-specific automated variance reduction techniques Presents Monte Carlo particle transport eigenvalue issues and methodologies to address these issues Presents detailed derivation of existing and advanced formulations and algorithms with real-world examples from the author’s research activities
Publisher: CRC Press
ISBN: 042958220X
Category : Mathematics
Languages : en
Pages : 214
Book Description
Fully updated with the latest developments in the eigenvalue Monte Carlo calculations and automatic variance reduction techniques and containing an entirely new chapter on fission matrix and alternative hybrid techniques. This second edition explores the uses of the Monte Carlo method for real-world applications, explaining its concepts and limitations. Featuring illustrative examples, mathematical derivations, computer algorithms, and homework problems, it is an ideal textbook and practical guide for nuclear engineers and scientists looking into the applications of the Monte Carlo method, in addition to students in physics and engineering, and those engaged in the advancement of the Monte Carlo methods. Describes general and particle-transport-specific automated variance reduction techniques Presents Monte Carlo particle transport eigenvalue issues and methodologies to address these issues Presents detailed derivation of existing and advanced formulations and algorithms with real-world examples from the author’s research activities
Scientific and Technical Aerospace Reports
Author:
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1460
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Publisher:
ISBN:
Category : Aeronautics
Languages : en
Pages : 1460
Book Description
Lists citations with abstracts for aerospace related reports obtained from world wide sources and announces documents that have recently been entered into the NASA Scientific and Technical Information Database.
Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards
Author: John S. Hendricks
Publisher: Springer Nature
ISBN: 3031041291
Category : Science
Languages : en
Pages : 316
Book Description
This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNP®) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors’ decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
Publisher: Springer Nature
ISBN: 3031041291
Category : Science
Languages : en
Pages : 316
Book Description
This open access book is a pedagogical, examples-based guide to using the Monte Carlo N-Particle (MCNP®) code for nuclear safeguards and non-proliferation applications. The MCNP code, general-purpose software for particle transport simulations, is widely used in the field of nuclear safeguards and non-proliferation for numerous applications including detector design and calibration, and the study of scenarios such as measurement of fresh and spent fuel. This book fills a gap in the existing MCNP software literature by teaching MCNP software usage through detailed examples that were selected based on both student feedback and the real-world experience of the nuclear safeguards group at Los Alamos National Laboratory. MCNP input and output files are explained, and the technical details used in MCNP input file preparation are linked to the MCNP code manual. Benefiting from the authors’ decades of experience in MCNP simulation, this book is essential reading for students, academic researchers, and practitioners whose work in nuclear physics or nuclear engineering is related to non-proliferation or nuclear safeguards. Each chapter comes with downloadable input files for the user to easily reproduce the examples in the text.
Monte Carlo Particle Transport Methods
Author: I. Lux
Publisher: CRC Press
ISBN: 1351083287
Category : Science
Languages : en
Pages : 530
Book Description
With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Publisher: CRC Press
ISBN: 1351083287
Category : Science
Languages : en
Pages : 530
Book Description
With this book we try to reach several more-or-less unattainable goals namely: To compromise in a single book all the most important achievements of Monte Carlo calculations for solving neutron and photon transport problems. To present a book which discusses the same topics in the three levels known from the literature and gives us useful information for both beginners and experienced readers. It lists both well-established old techniques and also newest findings.
Government Reports Announcements & Index
Particle Transport Simulation with the Monte Carlo Method
Author: Leland Lavele Carter
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 132
Book Description
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 132
Book Description
Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications
Author: Andreas Kling
Publisher: Springer
ISBN:
Category : Computers
Languages : en
Pages : 1224
Book Description
This book focuses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications. Special attention is paid to algorithm development for modeling, and the analysis of experiments and measurements in a variety of fields.
Publisher: Springer
ISBN:
Category : Computers
Languages : en
Pages : 1224
Book Description
This book focuses on the state of the art of Monte Carlo methods in radiation physics and particle transport simulation and applications. Special attention is paid to algorithm development for modeling, and the analysis of experiments and measurements in a variety of fields.
MCNP
Author: Judith F. Briesmeister
Publisher:
ISBN:
Category : Electron transport theory
Languages : en
Pages :
Book Description
Publisher:
ISBN:
Category : Electron transport theory
Languages : en
Pages :
Book Description
A Monte Carlo Code for the Transport of Neutrons
Author: William V. Baxter
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 40
Book Description
Publisher:
ISBN:
Category : Monte Carlo method
Languages : en
Pages : 40
Book Description