NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = M.MacInnes Found 5 matches. 2014CH24 Nucl.Data Sheets 118, 1 (2014) M.B.Chadwick, E.Dupont, E.Bauge, A.Blokhin, O.Bouland, D.A.Brown, R.Capote, A.Carlson, Y.Danon, C.De Saint Jean, M.Dunn, U.Fischer, R.A.Forrest, S.C.Frankle, T.Fukahori, Z.Ge, S.M.Grimes, G.M.Hale, M.Herman, A.Ignatyuk, M.Ishikawa, N.Iwamoto, O.Iwamoto, M.Jandel, R.Jacqmin, T.Kawano, S.Kunieda, A.Kahler, B.Kiedrowski, I.Kodeli, A.J.Koning, L.Leal, Y.O.Lee, J.P.Lestone, C.Lubitz, M.MacInnes, D.McNabb, R.McKnight, M.Moxon, S.Mughabghab, G.Noguere, G.Palmiotti, A.Plompen, B.Pritychenko, V.Pronyaev, D.Rochman, P.Romain, D.Roubtsov, P.Schillebeeckx, M.Salvatores, S.Simakov, E.Sh.Soukhovitskii, J.C.Sublet, P.Talou, I.Thompson, A.Trkov, R.Vogt, S.van der Marck The CIELO Collaboration: Neutron Reactions on 1H, 16O, 56Fe, 235, 238U, and 239Pu COMPILATION 1H, 16O, 56Fe, 235,238U, 239Pu(n, x), E≈0-20 MeV; analyzed available data on σ, neutron multiplicity, criticality using ENDF/B-VII.1, JENDL-4.0, JEFF-3.1, ROSFOND 2010, CENDL-3.1, EAF-2010 evaluated nuclear libraries, Atlas of Neutron Resonances, Neutron Cross Section Standards evaluations; deduced recommendations for CIELO library, parameters, Maxwellian-averaged, thermal, californium σ, Westcott factors, resonance integrals. Compared with available data.
doi: 10.1016/j.nds.2014.04.002
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
2011MA70 Nucl.Data Sheets 112, 3135 (2011) M.Mac Innes, M.B.Chadwick, T.Kawano Fission Product Yields for 14 MeV Neutrons on 235U, 238U and 239Pu
doi: 10.1016/j.nds.2011.11.009
2010CH41 Nucl.Data Sheets 111, 2923 (2010) M.B.Chadwick, T.Kawano, D.W.Barr, M.R.Mac Innes, A.C.Kahler, T.Graves, H.Selby, C.J.Burns, W.C.Inkret, A.L.Keksis, J.P.Lestone, A.J.Sierk, P.Talou Fission Product Yields from Fission Spectrum n+239Pu for ENDF/B-VII.1 NUCLEAR REACTIONS 239Pu(n, F)99Mo/95Zr/140Ba/144Ce/147Nd, E=0.2-2 MeV; measured fission products; deduced fission product yields and its energy dependence. Comparison with ENDF/B-VII.0 library, LANL-ILRR measurements.
doi: 10.1016/j.nds.2010.11.003
2010SE15 Nucl.Data Sheets 111, 2891 (2010) H.D.Selby, M.R.Mac Innes, D.W.Barr, A.L.Keksis, R.A.Meade, C.J.Burns, M.B.Chadwick, T.C.Wallstrom Fission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on 239Pu, 235U, 238U NUCLEAR REACTIONS 235,238U, 239Pu(n, F)99Mo/95Zr/137Cs/140Ba/141,143Ce/147Nd, E=0.4-1.9 MeV; measured fission products; deduced fission product yields. Comparison with ENDF/B-VII.0 library, BIG TEN critical assembly.
doi: 10.1016/j.nds.2010.11.002
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