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NSR database version of May 24, 2024.

Search: Author = R.C.Little

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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
Citations: PlumX Metrics


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
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23170.


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics


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
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset10956.


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)

R.C.Little, R.C.Block

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.


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