R
R. E. MacFarlane
Researcher at Los Alamos National Laboratory
Publications - 37
Citations - 5175
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.
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ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data
Mark B. Chadwick,M.W. Herman,P. Obložinský,Michael E Dunn,Yaron Danon,A.C. Kahler,David Livingstone Smith,Boris Pritychenko,Goran Arbanas,R. Arcilla,R. Brewer,David Brown,David Brown,Roberto Capote,Allan D. Carlson,Y.S. Cho,Herve Derrien,Klaus H Guber,Gerald M. Hale,S. Hoblit,S. Holloway,Timothy Johnson,Toshihiko Kawano,Brian C. Kiedrowski,H. Kim,S. Kunieda,S. Kunieda,Nancy M. Larson,Luiz C Leal,John Lestone,R. C. Little,E. A. McCutchan,R. E. MacFarlane,Michael MacInnes,Caleb Mattoon,R.D. McKnight,Said F. Mughabghab,Gustavo Nobre,Giuseppe Palmiotti,A. Palumbo,Marco T. Pigni,V.G. Pronyaev,R. O. Sayer,A. A. Sonzogni,N.C. Summers,Patrick Talou,Ian J. Thompson,Andrej Trkov,Ramona Vogt,S. C. van der Marck,Anton Wallner,Morgan C. White,Dorothea Wiarda,Phillip G. Young +53 more
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.
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.
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Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX
Mark B. Chadwick,Phillip G. Young,Satoshi Chiba,S.C. Frankle,Gerald M. Hale,H. G. Hughes,Arjan J. Koning,R. C. Little,R. E. MacFarlane,Richard E. Prael,Laurie S. Waters +10 more
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.
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Methods for Processing ENDF/B-VII with NJOY
R. E. MacFarlane,A.C. Kahler +1 more
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.
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A consistent set of neutron kerma coefficients from thermal to 150 MeV for biologically important materials.
Mark B. Chadwick,H. H. Barschall,Randall S. Caswell,Paul M. DeLuca,Gerald M. Hale,D. T. L. Jones,R. E. MacFarlane,J. P. Meulders,Helmut Schuhmacher,U.J. Schrewe,André Wambersie,Phillip G. Young +11 more
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.