O5r A General Purpose Monte Carlo Neutron Transport Code
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O5r A General Purpose Monte Carlo Neutron Transport Code
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Author : D. C. Irving
language : en
Publisher:
Release Date : 1965
O5r A General Purpose Monte Carlo Neutron Transport Code written by D. C. Irving and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1965 with Coding theory categories.
Mcnp A General Monte Carlo Code For Neutron And Photon Transport
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Author :
language : en
Publisher:
Release Date : 1979
Mcnp A General Monte Carlo Code For Neutron And Photon Transport written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with categories.
The general-purpose Monte Carlo code MCNP can be used for neutron, photon, or coupled neutron-photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces and some special fourth-degree surfaces (elliptical tori).
Mvp Gmvp Ii
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Author :
language : en
Publisher:
Release Date : 2005
Mvp Gmvp Ii written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2005 with Monte Carlo method categories.
Mcnp
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Author : Los Alamos Monte Carlo Group
language : en
Publisher:
Release Date : 1981
Mcnp written by Los Alamos Monte Carlo Group and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1981 with MCNP (Computer program) categories.
Mvp Gmvp Version 3
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Author :
language : en
Publisher:
Release Date : 2017
Mvp Gmvp Version 3 written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2017 with categories.
Mcnp
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Author :
language : en
Publisher:
Release Date : 1985
Mcnp written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1985 with categories.
MCNP is a very general Monte Carlo neutron photon transport code system with approximately 250 person years of Group X-6 code development invested. It is extremely portable, user-oriented, and a true production code as it is used about 60 Cray hours per month by about 150 Los Alamos users. It has as its data base the best cross-section evaluations available. MCNP contains state-of-the-art traditional and adaptive Monte Carlo techniques to be applied to the solution of an ever-increasing number of problems. Excellent user-oriented documentation is available for all facets of the MCNP code system. Many useful and important variants of MCNP exist for special applications. The Radiation Shielding Information Center (RSIC) in Oak Ridge, Tennessee is the contact point for worldwide MCNP code and documentation distribution. A much improved MCNP Version 3A will be available in the fall of 1985, along with new and improved documentation. Future directions in MCNP development will change the meaning of MCNP to Monte Carlo N Particle where N particle varieties will be transported.
Mcnp A General Monte Carlo Code For Neutron And Photon Transport
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Author : W. L. Thompson
language : en
Publisher:
Release Date :
Mcnp A General Monte Carlo Code For Neutron And Photon Transport written by W. L. Thompson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on with categories.
Mcnp
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Author : Los Alamos Scientific Laboratory. Group X-6
language : en
Publisher:
Release Date : 1979
Mcnp written by Los Alamos Scientific Laboratory. Group X-6 and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with Monte Carlo method categories.
Monte Carlo N Particle Simulations For Nuclear Detection And Safeguards
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Author : John S. Hendricks
language : en
Publisher: Springer Nature
Release Date : 2022-09-27
Monte Carlo N Particle Simulations For Nuclear Detection And Safeguards written by John S. Hendricks and has been published by Springer Nature this book supported file pdf, txt, epub, kindle and other format this book has been release on 2022-09-27 with Science categories.
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.
Mvp Gmvp Ii General Purpose Monte Carlo Codes For Neutron And Photon Transport Calculations Based On Continous Energy And Multigroup Methods
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Author : Yasunobu Nagaya
language : en
Publisher:
Release Date : 2004
Mvp Gmvp Ii General Purpose Monte Carlo Codes For Neutron And Photon Transport Calculations Based On Continous Energy And Multigroup Methods written by Yasunobu Nagaya and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 2004 with categories.
