scispace - formally typeset
Search or ask a question
Author

R. E. MacFarlane

Bio: R. E. MacFarlane is an academic researcher from Los Alamos National Laboratory. The author has contributed to research in topics: Nuclear data & Neutron. The author has an hindex of 13, co-authored 37 publications receiving 4612 citations.

Papers
More filters
Journal ArticleDOI
TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.

2,171 citations

Journal ArticleDOI
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.

1,913 citations

Journal ArticleDOI
TL;DR: In this article, the GNASH nuclear model code is used to calculate cross sections using Hauser-Feshbach, exciton, and Feshbach-Kerman-Koonin preequilibrium models.
Abstract: New accelerator-driven technologies that utilize spallation neutrons, such as the production of tritium and the transmutation of radioactive waste, require accurate nuclear data to model the performance of the target/blanket assembly and to predict neutron production, activation, heating, shielding requirements, and material damage. To meet these needs, nuclear-data evaluations and libraries up to 150 MeV have been developed for use in transport calculations to guide engineering design. By using advanced nuclear models that account for details of nuclear structure and the quantum nature of the nuclear scattering, significant gains in accuracy can be achieved below 150 MeV, where intranuclear cascade calculations become less accurate. Evaluations are in ENDF-6 format for important target/blanket and shielding materials (isotopes of H, C, N, O, Al, Si, P, Ca, Cr, Fe, Ni, Cu, Nb, W, Hg, and Pb) for both incident neutrons and incident protons. The evaluations are based on measured data as well as predictions from the GNASH nuclear model code, which calculates cross sections using Hauser-Feshbach, exciton, and Feshbach-Kerman-Koonin preequilibrium models. Elastic scattering distributions and direct reactions are calculated from the optical model. All evaluations specify production cross sections and energy-angle correlated spectra of secondary light particles as well as production crossmore » sections and energy distributions of heavy recoils and gamma rays. A formalism developed to calculate recoil energy distributions is presented. The use of these nuclear data in the MCNPX radiation transport code is also briefly described. This code merges essential elements of the LAHET and MCNP codes and uses these new data below 150 MeV and intranuclear cascade collision physics at higher energies. Extensive comparisons are shown between the evaluated results and experimental cross-section data to benchmark and validate the evaluated library. In addition, integral benchmarks of calculated and measured kerma coefficients for neutron energy deposition and neutron transmission through an iron slab compared with MCNPX calculations are provided. These evaluations have been accepted into the ENDF/B-VI library as Release 6.« less

339 citations

Journal ArticleDOI
TL;DR: The NJOY Nuclear Data Processing System is widely used to convert evaluations in the Evaluated Nuclear Data Files (ENDF) format into forms useful for practical applications such as fission and fusion reactor analysis, stockpile stewardship calculations, criticality safety, radiation shielding, nuclear waste management, nuclear medicine procedures, and more.

333 citations

Journal ArticleDOI
TL;DR: Kerma coefficients are derived from the neutron cross sections, for major isotopes of H, C, N, O, Al, Si, P, Ca, Fe, Cu, W, Pb, and for ICRU-muscle, A-150 tissue-equivalent plastic, and other compounds important for treatment planning and dosimetry.
Abstract: Neutron cross sections for nonelastic and elastic reactions on a range of elements have been evaluated for incident energies up to 150 MeV. These cross sections agree well with experimental cross section data for charged-particle production as well as neutron and photon production. Therefore they can be used to determine kerma coefficients for calculations of energy deposition by neutrons in matter. Methods used to evaluate the neutron cross sections above 20 MeV, using nuclear model calculations and experimental data, are described. Below 20 MeV, the evaluated cross sections from the ENDF/B-VI library are adopted. Comparisons are shown between the evaluated charged-particle production cross sections and measured data. Kerma coefficients are derived from the neutron cross sections, for major isotopes of H, C, N, O, Al, Si, P, Ca, Fe, Cu, W, Pb, and for ICRU-muscle, A-150 tissue-equivalent plastic, and other compounds important for treatment planning and dosimetry. Numerous comparisons are made between our kerma coefficients and experimental kerma coefficient data, to validate our results, and agreement is found to be good. An important quantity in neutron dosimetry is the kerma coefficient ratio of ICRU-muscle to A-150 plastic. When this ratio is calculated from our kerma coefficient data, and averaged over more » the neutron energy spectra for higher-energy clinical therapy beams [three p(68)+Be beams, and a d(48.5)+Be beam], a value of 0.94{plus_minus}0.03 is obtained. Kerma ratios for water to A-150 plastic, and carbon to oxygen, are also compared with measurements where available. {copyright} {ital 1999 American Association of Physicists in Medicine.} « less

89 citations


Cited by
More filters
Journal ArticleDOI
John Allison1, K. Amako2, John Apostolakis3, Pedro Arce4, Makoto Asai5, Tsukasa Aso6, Enrico Bagli, Alexander Bagulya7, Sw. Banerjee8, G. Barrand9, B. R. Beck10, Alexey Bogdanov11, D. Brandt, Jeremy M. C. Brown12, Helmut Burkhardt3, Ph Canal8, D. Cano-Ott4, Stephane Chauvie, Kyung-Suk Cho13, G.A.P. Cirrone14, Gene Cooperman15, M. A. Cortés-Giraldo16, G. Cosmo3, Giacomo Cuttone14, G.O. Depaola17, Laurent Desorgher, X. Dong15, Andrea Dotti5, Victor Daniel Elvira8, Gunter Folger3, Ziad Francis18, A. Galoyan19, L. Garnier9, M. Gayer3, K. Genser8, Vladimir Grichine3, Vladimir Grichine7, Susanna Guatelli20, Susanna Guatelli21, Paul Gueye22, P. Gumplinger23, Alexander Howard24, Ivana Hřivnáčová9, S. Hwang13, Sebastien Incerti25, Sebastien Incerti26, A. Ivanchenko3, Vladimir Ivanchenko3, F.W. Jones23, S. Y. Jun8, Pekka Kaitaniemi27, Nicolas A. Karakatsanis28, Nicolas A. Karakatsanis29, M. Karamitrosi30, M.H. Kelsey5, Akinori Kimura31, Tatsumi Koi5, Hisaya Kurashige32, A. Lechner3, S. B. Lee33, Francesco Longo34, M. Maire, Davide Mancusi, A. Mantero, E. Mendoza4, B. Morgan35, K. Murakami2, T. Nikitina3, Luciano Pandola14, P. Paprocki3, J Perl5, Ivan Petrović36, Maria Grazia Pia, W. Pokorski3, J. M. Quesada16, M. Raine, Maria A.M. Reis37, Alberto Ribon3, A. Ristic Fira36, Francesco Romano14, Giorgio Ivan Russo14, Giovanni Santin38, Takashi Sasaki2, D. Sawkey39, J. I. Shin33, Igor Strakovsky40, A. Taborda37, Satoshi Tanaka41, B. Tome, Toshiyuki Toshito, H.N. Tran42, Pete Truscott, L. Urbán, V. V. Uzhinsky19, Jerome Verbeke10, M. Verderi43, B. Wendt44, H. Wenzel8, D. H. Wright5, Douglas Wright10, T. Yamashita, J. Yarba8, H. Yoshida45 
TL;DR: Geant4 as discussed by the authors is a software toolkit for the simulation of the passage of particles through matter, which is used by a large number of experiments and projects in a variety of application domains, including high energy physics, astrophysics and space science, medical physics and radiation protection.
Abstract: Geant4 is a software toolkit for the simulation of the passage of particles through matter. It is used by a large number of experiments and projects in a variety of application domains, including high energy physics, astrophysics and space science, medical physics and radiation protection. Over the past several years, major changes have been made to the toolkit in order to accommodate the needs of these user communities, and to efficiently exploit the growth of computing power made available by advances in technology. The adaptation of Geant4 to multithreading, advances in physics, detector modeling and visualization, extensions to the toolkit, including biasing and reverse Monte Carlo, and tools for physics and release validation are discussed here.

2,260 citations

Journal ArticleDOI
TL;DR: The ENDF/B-VII.1 library as mentioned in this paper is the most widely used data set for nuclear data analysis and has been updated several times over the last five years. But the most recent version of the ENDF-B-VI.0 library is based on the JENDL-4.0 standard.

2,171 citations

Journal ArticleDOI
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.

1,913 citations

Journal ArticleDOI
TL;DR: The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee as mentioned in this paper, and much emphasis is placed on the improvement of the original library.
Abstract: The fourth version of the Japanese Evaluated Nuclear Data Library has been produced in cooperation with the Japanese Nuclear Data Committee. In the new library, much emphasis is placed on the impro...

1,699 citations

Journal ArticleDOI
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.

1,249 citations