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MCNP-A General Monte Carlo N-Particle Transport Code
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In this article, the authors present a practical guide for the use of general-purpose Monte Carlo code MCNP, including several examples and a discussion of the particular techniques and the Monte Carlo method itself.Abstract:
This manual is a practical guide for the use of our general-purpose Monte Carlo code MCNP. The first chapter is a primer for the novice user. The second chapter describes the mathematics, data, physics, and Monte Carlo simulation found in MCNP. This discussion is not meant to be exhaustive---details of the particular techniques and of the Monte Carlo method itself will have to be found elsewhere. The third chapter shows the user how to prepare input for the code. The fourth chapter contains several examples, and the fifth chapter explains the output. The appendices show how to use MCNP on various computer systems and also give details about some of the code internals.read more
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Journal ArticleDOI
ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Mark B. Chadwick,P. Obložinský,M.W. Herman,N.M. Greene,R.D. McKnight,David Livingstone Smith,Phillip G. Young,R. E. MacFarlane,Gerald M. Hale,S.C. Frankle,A.C. Kahler,Toshihiko Kawano,R. C. Little,D. G. Madland,Peter Möller,Russell D. Mosteller,Philip R. Page,Patrick Talou,Holly R. Trellue,Morgan C. White,William B. Wilson,R. Arcilla,C.L. Dunford,Said F. Mughabghab,Boris Pritychenko,D. Rochman,Alejandro Sonzogni,C.R. Lubitz,T.H. Trumbull,J.P. Weinman,David Brown,D.E. Cullen,David P. Heinrichs,D. P. McNabb,Herve Derrien,Michael E Dunn,Nancy M. Larson,Luiz C Leal,Allan D. Carlson,R.C. Block,J.B. Briggs,E.T. Cheng,H.C. Huria,M.L. Zerkle,K.S. Kozier,A. Courcelle,V.G. Pronyaev,S. C. van der Marck +47 more
TL;DR: The ENDF/B-VII.0 as discussed by the authors file contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes, based on experimental data and theory predictions.
Journal ArticleDOI
GATE : a simulation toolkit for PET and SPECT
Sébastien Jan,Giovanni Santin,D. Strul,D. Strul,Steven Staelens,Karine Assié,D. Autret,Stéphane Avner,Remi Barbier,Manuel Bardiès,Peter M. Bloomfield,David Brasse,Vincent Breton,P. Bruyndonckx,Irène Buvat,Arion F. Chatziioannou,Yong Choi,Y. H. Chung,Claude Comtat,D. Donnarieix,Ludovic Ferrer,Stephen J. Glick,C. J. Groiselle,David Guez,P. F. Honore,S. Kerhoas-Cavata,Assen S. Kirov,V. Kohli,Michel Koole,M. Krieguer,D.J. van der Laan,F. Lamare,G. Largeron,Carole Lartizien,D. Lazaro,Marnix C. Maas,Lydia Maigne,F. Mayet,F. Melot,C. Merheb,E. Pennacchio,J. Perez,Uwe Pietrzyk,F. R. Rannou,F. R. Rannou,M. Rey,Dennis R. Schaart,Charles Schmidtlein,Luc Simon,Luc Simon,Tae Yong Song,J. M. Vieira,Dimitris Visvikis,R. T. Van de Walle,E. Wieers,Christian Morel +55 more
TL;DR: A detailed description of the design and development of GATE is given by the OpenGATE collaboration, whose continuing objective is to improve, document and validate GATE by simulating commercially available imaging systems for PET and SPECT.
PENELOPE-2006: A Code System for Monte Carlo Simulation of Electron and Photon Transport
TL;DR: The PENELOPE as mentioned in this paper computer code system performs Monte Carlo simulation of coupled electron-photon transport in arbitrary materials for a wide energy range, from a few hundred eV to about 1 GeV.
Journal ArticleDOI
Update of AAPM Task Group No. 43 Report: A revised AAPM protocol for brachytherapy dose calculations.
Mark J. Rivard,Bert M. Coursey,Larry A. DeWerd,William F. Hanson,M. Saiful Huq,Geoffrey S. Ibbott,Michael G. Mitch,Ravinder Nath,Jeffrey F. Williamson +8 more
TL;DR: An update of the TG-43 protocol for calculation of dose-rate distributions around photon-emitting brachytherapy sources is presented, and a unified approach to comparing reference dose distributions derived from different investigators to develop a single critically evaluated consensus dataset is recommended.
Journal ArticleDOI
ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data
David Brown,Mark B. Chadwick,Roberto Capote,A.C. Kahler,Andrej Trkov,M.W. Herman,A. A. Sonzogni,Yaron Danon,Allan D. Carlson,Michael E Dunn,D.L. Smith,Gerald M. Hale,Goran Arbanas,R. Arcilla,C.R. Bates,B. Beck,B. Becker,Forrest B. Brown,R.J. Casperson,Jeremy Lloyd Conlin,D.E. Cullen,M.-A. Descalle,Richard B. Firestone,T. Gaines,Klaus H Guber,Ayman I. Hawari,Jesse C. Holmes,Timothy Johnson,Toshihiko Kawano,Brian C. Kiedrowski,Arjan J. Koning,Stefan Kopecky,Luiz Leal,John Lestone,C.R. Lubitz,J.I. Márquez Damián,Caleb Mattoon,E. A. McCutchan,Said F. Mughabghab,Petr Navrátil,Denise Neudecker,Gustavo Nobre,Gilles Noguere,Mark W. Paris,Marco T. Pigni,A. J. M. Plompen,Boris Pritychenko,V.G. Pronyaev,D. Roubtsov,D. Rochman,Paul K. Romano,Peter Schillebeeckx,Stanislav Simakov,M. Sin,I. Sirakov,Brad W. Sleaford,Vladimir Sobes,E.S. Soukhovitskii,Ionel Stetcu,Patrick Talou,Ian J. Thompson,S. C. van der Marck,L. Welser-Sherrill,Dorothea Wiarda,Morgan C. White,J.L. Wormald,R.Q. Wright,M.L. Zerkle,G. Žerovnik,Y. Zhu +69 more
TL;DR: The new ENDF/B-VIII.0 evaluated nuclear reaction data library as mentioned in this paper includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu described in companion papers.
References
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ReportDOI
Data formats and procedures for the Evaluated Nuclear Data File, ENDF
TL;DR: The ENDF system as mentioned in this paper is composed of several parts that include a series of data processing codes and neutron and photon cross section nuclear structure libraries, and is designed for storage and retrieval of the evaluated nuclear data that are required for neutronics, photonics and decay heat calculations.
Journal ArticleDOI
MCNP capabilities for nuclear well logging calculations
TL;DR: The Los Alamos Radiation Transport Code System (LARTCS) as discussed by the authors consists of state-of-the-art Monte Carlo and discrete ordinates transport codes and data libraries.
ReportDOI
ACTL: evaluated neutron activation cross section library-evaluation techniques and reaction index. [Tables, 10/sup -10/ to 20 MeV]
Gardner,R.J. Howerton +1 more
TL;DR: A library of evaluated neutron-induced activation cross sections (ACTL) was compiled and general descriptions of the evaluation methods and an index to the evaluated cross sections are presented.
ReportDOI
Average neutronic properties of prompt fission products
D.G. Foster,E.D. Arthur +1 more
TL;DR: In this paper, the average neutronic properties of the ensemble of fission products producted by fast-neutron fission of /sup 235/U and /sup 239/Pu, where the properties are determined before the first beta decay of any of the fragments, are described.
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ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Mark B. Chadwick,P. Obložinský,M.W. Herman,N.M. Greene,R.D. McKnight,David Livingstone Smith,Phillip G. Young,R. E. MacFarlane,Gerald M. Hale,S.C. Frankle,A.C. Kahler,Toshihiko Kawano,R. C. Little,D. G. Madland,Peter Möller,Russell D. Mosteller,Philip R. Page,Patrick Talou,Holly R. Trellue,Morgan C. White,William B. Wilson,R. Arcilla,C.L. Dunford,Said F. Mughabghab,Boris Pritychenko,D. Rochman,Alejandro Sonzogni,C.R. Lubitz,T.H. Trumbull,J.P. Weinman,David Brown,D.E. Cullen,David P. Heinrichs,D. P. McNabb,Herve Derrien,Michael E Dunn,Nancy M. Larson,Luiz C Leal,Allan D. Carlson,R.C. Block,J.B. Briggs,E.T. Cheng,H.C. Huria,M.L. Zerkle,K.S. Kozier,A. Courcelle,V.G. Pronyaev,S. C. van der Marck +47 more