NSR Query Results
Output year order : Descending NSR database version of April 26, 2024. Search: Author = R.E.MacFarlane Found 13 matches. 2014KA31 Nucl.Data Sheets 118, 410 (2014) A.C.Kahler, R.E.MacFarlane, M.B.Chadwick Integral Data Testing of ENDF/B-VII.1 Files - Success Stories and Need to Improve Stories
doi: 10.1016/j.nds.2014.04.093
2011CH57 Nucl.Data Sheets 112, 2887 (2011) M.B.Chadwick, M.Herman, P.Oblozinsky, M.E.Dunn, Y.Danon, A.C.Kahler, D.L.Smith, B.Pritychenko, G.Arbanas, R.Arcilla, R.Brewer, D.A.Brown, R.Capote, A.D.Carlson, Y.S.Cho, H.Derrien, K.Guber, G.M.Hale, S.Hoblit, S.Holloway, T.D.Johnson, T.Kawano, B.C.Kiedrowski, H.Kim, S.Kunieda, N.M.Larson, L.Leal, J.P.Lestone, R.C.Little, E.A.McCutchan, R.E.MacFarlane, M.MacInnes, C.M.Mattoon, R.D.McKnight, S.F.Mughabghab, G.P.A.Nobre, G.Palmiotti, A.Palumbo, M.T.Pigni, V.G.Pronyaev, R.O.Sayer, A.A.Sonzogni, N.C.Summers, P.Talou, I.J.Thompson, A.Trkov, R.L.Vogt, S.C.van der Marck, A.Wallner, M.C.White, D.Wiarda, P.G.Young ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data COMPILATION Z=1-118; compiled, analyzed decay data, Maxwellian averaged neutron capture σ, neutron-induced fission σ. NUCLEAR REACTIONS 1,2H, 3He, 6,7Li, 7,9Be, 10,11B, C, 14,15N, 16,17O, 19F, 22,23Na, 24,25,26Mg, 27Al, 28,29,30Si, 31P, 32,33,34,36S, 35,37Cl, 36,38,40Ar, 39,40,41K, 40,42,43,44,46,48Ca, 45Sc, 46,47,48,49,50Ti, 50,51V, 50,52,53,54Cr, 55Mn, 54,56,57,58Fe, 58,59Co, 58,59,60,61,62,64Ni, 63,65Cu, 65,66,67,68,70Zn, 69,71Ga, 70,72,73,74,76Ge, 74,75As, 74,76,77,78,79,80,82Se, 79,81Br, 78,80,82,83,84,85,86Kr, 85,86,87Rb, 84,86,87,88,89,90Sr, 89,90,91Y, 90,91,92,93,94,95,96Zr, 93,94,95Nb, 92,94,95,96,97,98,99,100Mo, 99Tc, 96,98,99,100,101,102,103,104,105,106Ru, 103,105Rh, 102,104,105,106,107,108,110Pd, 107,109,110,111Ag, 106,108,110,111,112,113,114,115,116Cd, 113,115In, 112,113,114,115,116,117,118,119,120,122,123,124,125,126Sn, 121,123,124,125,126Sb, 120,122,123,124,125,126,127,128,129,130,132Te, 127,129,130,131,135I, 123,124,126,128,129,130,131,132,133,134,135,136Xe, 133,134,135,136,137Cs, 130,132,133,134,135,136,137,138,140Ba, 138,139,140La, 136,138,139,140,141,142,143,144Ce, 141,142,143Pr, 142,143,144,145,146,147,148,150Nd, 147,148,149,151Pm, 144,147,148,149,150,151,152,153,154Sm, 151,152,153,154,155,156,157Eu, 152,153,154,155,156,157,158,160Gd, 159,160Tb, 156,158,160,161,162,163,164Dy, 165,166Ho, 162,164,166,167,168,170Er, 168,169,170Tm, 175,176Lu, 174,176,177,178,179,180Hf, 180,181,182Ta, 180,182,183,184,186W, 185,187Re, 191,193Ir, 197Au, 196,198,199,200,201,202,204Hg, 203,205Tl, 204,206,207,208Pb, 209Bi, 223,224,225,226Ra, 225,226,227Ac, 227,228,229,230,231,232,233,234Th, 229,230,231,232,233Pa, 230,231,232,233,234,235,236,237,238,239,240,241U, 234,235,236,237,238,239Np, 236,237,238,239,240,241,242,243,244,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,249,250Bk, 246,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), E=30 keV; calculated Maxwellian-averaged σ using ENDF/B-VII.1 evaluated neutron library. Comparison with ENDF/B-VII.0 and KADONIS values. NUCLEAR REACTIONS 227,228,229,230,231,232,233,234Th, 229,230,231,232,233Pa, 230,231,232,233,234,235,236,237,238,239,240,241U, 234,235,236,237,238,239Np, 236,237,238,239,240,241,242,243,244,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,249,250Bk, 246,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), (n, F), E=thermal; calculated thermal σ. Comparison with ENDF/B-VII.0, JENDL-4.0 and Atlas of Neutron Resonances values.
doi: 10.1016/j.nds.2011.11.002
2011KA31 Nucl.Data Sheets 112, 2997 (2011) A.C.Kahler, R.E.MacFarlane, R.D.Mosteller, B.C.Kiedrowski, S.C.Frankle, M.B.Chadwick, R.D.McKnight, R.M.Lell, G.Palmiotti, H.Hiruta, M.Herman, R.Arcilla, S.F.Mughabghab, J.C.Sublet, A.Trkov, T.H.Trumbull, M.Dunn ENDF/B-VII.1 Neutron Cross Section Data Testing with Critical Assembly Benchmarks and Reactor Experiments
doi: 10.1016/j.nds.2011.11.003
2010MA55 Nucl.Data Sheets 111, 2739 (2010) Methods for Processing ENDF/B-VII with NJOY
doi: 10.1016/j.nds.2010.11.001
2009SU12 Nucl.Technology 168, 293 (2009) J.-Ch.Sublet, D.E.Cullen, R.E.MacFarlane How Accurately Can We Calculate Fast Neutrons Slowing Down in Water?
doi: 10.13182/NT09-A9197
2007CH79 Nucl.Data Sheets 108, 2716 (2007) M.B.Chadwick, S.Frankle, H.Trellue, P.Talou, T.Kawano, P.G.Young, R.E.MacFarlane, C.W.Wilkerson Evaluated Iridium, Yttrium, and Thulium Cross Sections and Integral Validation Against Critical Assembly and Bethe Sphere Measurements NUCLEAR REACTIONS 89Y, 168,169Tm, 191,193Ir(n, X), E< 30 MeV; evaluated cross sections.
doi: 10.1016/j.nds.2007.11.005
2007TA01 Nucl.Sci.Eng. 155, 84 (2007) P.Talou, T.Kawano, P.G.Young, M.B.Chadwick, R.E.MacFarlane Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes NUCLEAR REACTIONS 241,242,243Am(n, γ), (n, 2n), (n, F), (n, X), E < 20 MeV; compiled, analyzed σ, prompt neutron fission multiplicity.
doi: 10.13182/NSE07-A2646
2007YO07 Nucl.Data Sheets 108, 2589 (2007) P.G.Young, M.B.Chadwick, R.E.MacFarlane, P.Talou, T.Kawano, D.G.Madland, W.B.Wilson, C.W.Wilkerson Evaluation of Neutron Reactions for ENDF/B-VII:232-241U and 239PU NUCLEAR REACTIONS 232,233,234,235,236,237,239,240,241U, 239Pu(n, X), E< 30 MeV; evaluated cross sections for ENDF/B-VII.
doi: 10.1016/j.nds.2007.11.002
2006CH50 Nucl.Data Sheets 107, 2931 (2006) M.B.Chadwick, P.Oblozinsky, M.Herman, N.M.Greene, R.D.McKnight, D.L.Smith, P.G.Young, R.E.MacFarlane, G.M.Hale, S.C.Frankle, A.C.Kahler, T.Kawano, R.C.Little, D.G.Madland, P.Moller, R.D.Mosteller, P.R.Page, P.Talou, H.Trellue, M.C.White, W.B.Wilson, R.Arcilla, C.L.Dunford, S.F.Mughabghab, B.Pritychenko, D.Rochman, A.A.Sonzogni, C.R.Lubitz, T.H.Trumbull, J.P.Weinman, D.A.Brown, D.E.Cullen, D.P.Heinrichs, D.P.McNabb, H.Derrien, M.E.Dunn, N.M.Larson, L.C.Leal, A.D.Carlson, R.C.Block, J.B.Briggs, E.T.Cheng, H.C.Huria, M.L.Zerkle, K.S.Kozier, A.Courcelle, V.Pronyaev, S.C.van der Marck ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
doi: 10.1016/j.nds.2006.11.001
2003CH80 Nucl.Sci.Eng. 144, 157 (2003) M.B.Chadwick, P.G.Young, R.E.MacFarlane, M.C.White, R.C.Little Photonuclear Physics in Radiation Transport - I: Cross Sections and Spectra NUCLEAR REACTIONS 206,207,208Pb, 184W, 181Ta, 63Cu, 40Ca, 28Si, 27Al, 16O, 12C(γ, X), (γ, nX), E < 150 MeV; calculated absorption, photoneutron production σ. Comparison with data.
doi: 10.13182/NSE144-157
2003WH01 Nucl.Sci.Eng. 144, 174 (2003) M.C.White, R.C.Little, M.B.Chadwick, P.G.Young, R.E.MacFarlane Photonuclear Physics in Radiation Transport - II: Implementation
doi: 10.13182/NSE144-174
1999CH14 Nucl.Sci.Eng. 131, 293 (1999) M.B.Chadwick, P.G.Young, S.Chiba, S.C.Frankle, G.M.Hale, H.G.Hughes, A.J.Koning, R.C.Little, R.E.MacFarlane, R.E.Prael, L.S.Waters Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX NUCLEAR REACTIONS H, C, N, O, 27Al, Si, P, Ca, Cr, Fe, Ni, Cu, Nb, W, Hg, Pb(n, X), (p, X), E < 150 MeV; compiled, evaluated σ, σ(θ).
doi: 10.13182/NSE98-48
1989YO11 Trans.Amer.Nucl.Soc. 60, 271 (1989) P.G.Young, E.D.Arthur, M.Bozoian, T.R.England, G.M.Hale, R.J.LaBauve, R.C.Little, R.E.MacFarlane, D.G.Madland, R.T.Perry, W.B.Wilson 7. Transport data libraries for incident proton and neutron energies to 100 MeV NUCLEAR REACTIONS 1H, 9Be, C, O, 27Al, Si, Fe, W, 238U(p, X), 1H, 9Be, C, O, 27Al, Si, Ca, Fe, W, 238U(n, X), E<100 MeV; analyzed available data; deduced σ for transport libraries.
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