NSR Query Results
Output year order : Descending NSR database version of April 26, 2024. Search: Author = R.C.Little Found 18 matches. 2021SO30 Nucl.Technology 207, s100 (2021) A.Sood, R.A.Forster, B.J.Archer, R.C.Little Neutronics Calculation Advances at Los Alamos: Manhattan Project to Monte Carlo
doi: 10.1080/00295450.2021.1956255
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
2010TA15 Nucl.Sci.Eng. 166, 254 (2010) P.Talou, T.Kawano, D.G.Madland, A.C.Kahler, D.K.Parsons, M.C.White, R.C.Little, M.B.Chadwick Uncertainty Quantification of Prompt Fission Neutron Spectrum for n(0.5 MeV) + 239Pu NUCLEAR REACTIONS 239Pu(n, F), E<0.5 MeV; calculated fission spectrum uncertainties, probability distribution functions; deduced correlation matrix. Madland-Nix model.
doi: 10.13182/NSE09-10
2009CH04 Ann.Nucl.Energy 36, 258 (2009) M.B.Chadwick, R.C.Little, T.Kawano, P.Talou, D.Viera, M.Jandel, T.A.Bredeweg, M.C.White, A.P.Tonchev, J.A.Becker Actinide ENDF/B-VII cross-section evaluations and validation testing NUCLEAR REACTIONS 241Am(n, γ), E < 1000 MeV; 241Am(n, 2n), E < 20 MeV; analyzed cross sections. 239Pu(n, X), E=1.0 MeV; 238U(n, γ), E < 1.0 MeV; calculated cross sections.
doi: 10.1016/j.anucene.2008.11.011
2008KA38 Nucl.Data Sheets 109, 2817 (2008) T.Kawano, P.Talou, P.G.Young, G.Hale, M.B.Chadwick, R.C.Little Evaluation of Covariances for Actinides and Light Elements at LANL
doi: 10.1016/j.nds.2008.11.016
2008LI51 Nucl.Data Sheets 109, 2828 (2008) R.C.Little, T.Kawano, G.D.Hale, M.T.Pigni, M.Herman, P.Oblozinsky, M.L.Williams, M.E.Dunn, G.Arbanas, D.Wiarda, R.D.McKnight, J.N.McKamy, J.R.Felty Low-fidelity Covariance Project
doi: 10.1016/j.nds.2008.11.018
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
2006KA13 Nucl.Sci.Eng. 153, 1 (2006) T.Kawano, K.M.Hanson, S.Frankle, P.Talou, M.B.Chadwick, R.C.Little Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique NUCLEAR REACTIONS 239Pu(n, F), E < 20 MeV; analyzed fission σ; deduced covariances in uncertainties. Monte Carlo technique.
doi: 10.13182/NSE06-A2589
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
2001CH92 Prog.Nucl.Energy 38, 179 (2001) M.B.Chadwick, H.G.Hughes, R.C.Little, E.J.Pitcher, P.G.Young Nuclear Data for Accelerator-Driven Systems NUCLEAR REACTIONS Pb(n, X), (n, n), E=20-150 MeV; compiled, evaluated σ, σ(θ). 184W, 209Bi(n, xn), E=20-150 MeV; C, Al, Fe, Cu, 208Pb, 209Bi(p, xn), E=30-113 MeV; compiled, evaluated neutron spectra. Applications to accelerator-driven systems discussed.
doi: 10.1016/S0149-1970(00)00102-5
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.
1988RA13 Nucl.Sci.Eng. 98, 357 (1988) P.Ramakrishnan, G.E.Mitchell, C.R.Gould, S.A.Wender, G.F.Auchampaugh, R.C.Little Neutron-Induced Photon Production Cross Sections NUCLEAR REACTIONS Ta(n, X), E < 20 MeV; measured Eγ, Iγ, photon production σ(E, Eγ); deduced σ(E).
doi: 10.13182/NSE88-A23536
1986GO14 Radiat.Eff. 92, 139 (1986) C.R.Gould, J.Dave, G.E.Mitchell, P.Ramakrishnan, G.F.Auchampaugh, R.C.Little, S.A.Wender Photon Production Cross Section Measurements for Ta and Be NUCLEAR REACTIONS Ta, 9Be(n, γ), E=2-25 MeV; measured γ-ray production σ.
doi: 10.1080/00337578608208307
1981LI16 Nucl.Sci.Eng. 79, 175 (1981) R.C.Little, R.C.Block, D.R.Harris, R.E.Slovacek, O.N.Carlson Neutron Capture and Total Cross Section of Thorium-232 from 0.006 to 18 eV NUCLEAR REACTIONS 232Th(n, γ), (n, X), E=0.006-18 eV; measured σ(E), transmission; deduced σ(total, E). Liquid scintillator, 6Li glass neutron detectors.
doi: 10.13182/NSE81-A27406
1979LI20 Trans.Amer.Nucl.Soc. 32, 748 (1979) R.C.Little, R.C.Block, D.R.Harris, O.N.Carlson The Neutron Total Cross Section of 232Th from 0.1 to 18 eV NUCLEAR REACTIONS 232Th(n, X), E0.1-18 eV; measured reaction products, En, In; deduced σ. Data from this article have been entered in the EXFOR database. For more information, access X4 dataset10956. 1977LI23 Trans.Amer.Nucl.Soc. 26, 574 (1977) Neutron Capture Cross-Section Measurements of 99Tc up to 80 keV NUCLEAR REACTIONS 99Tc(n, γ), E<80 keV; measured reaction products, En, In, Eγ, Iγ; deduced σ, resonance parameters. Data from this article have been entered in the EXFOR database. For more information, access X4 dataset10671. Back to query form |