NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = N.M.Larson Found 19 matches. 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
2009CA28 Nucl.Data Sheets 110, 3215 (2009) A.D.Carlson, V.G.Pronyaev, D.L.Smith, N.M.Larson, Z.Chen, G.M.Hale, F.-J.Hambsch, E.V.Gai, S.-Y.Oh, S.A.Badikov, T.Kawano, H.M.Hofmann, H.Vonach, S.Tagesen International Evaluation of Neutron Cross Section Standards
doi: 10.1016/j.nds.2009.11.001
2009DE04 Nucl.Sci.Eng. 161, 131 (2009) H.Derrien, A.Courcelle, L.C.Leal, N.M.Larson R-Matrix Analysis of 238U High-Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 to 20 keV NUCLEAR REACTIONS 238U(n, γ), E=0-20 keV; analyzed capture cross sections;deduced resonance parameters. R-matrix analysis.
doi: 10.13182/NSE161-131
2008CA28 Nucl.Data Sheets 109, 2834 (2008) A.D.Carlson, S.A.Badikov, Z.Chen, E.Gai, G.M.Hale, F.-J.Hambsch, H.M.Hofmann, T.Kawano, N.M.Larson, S.Y.Oh, V.G.Pronyaev, D.L.Smith, S.Tagesen, H.Vonach Covariances Obtained from an Evaluation of the Neutron Cross Section Standards NUCLEAR REACTIONS 6Li(n, t), E < 1 MeV; 10B(n, α), E < 1 MeV; analyzed cross sections.
doi: 10.1016/j.nds.2008.11.019
2008DE20 Nucl.Sci.Eng. 160, 149 (2008) H.Derrien, L.C.Leal, N.M.Larson R-Matrix Analysis of 232Th Neutron Transmissions and Capture Cross Sections in the Energy Range Thermal to 4 keV NUCLEAR REACTIONS 232Th(n, γ), (n, X), E < 4 keV; analyzed cross sections using the SAMMY R-matrix analysis code.
doi: 10.13182/NSE160-149
2007CO16 Nucl.Sci.Eng. 156, 391 (2007) A.Courcelle, H.Derrien, L.C.Leal, N.M.Larson Evaluation of the 238U Neutron Cross Section in the Unresolved Resonance Range NUCLEAR REACTIONS 238U(n, X), E=20-150 keV; analyzed cross sections in the unresolved resonance range. Deduced average resonance parameters. Compared results to existing evaluations.
doi: 10.13182/NSE07-A2706
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
2006SA17 Phys.Rev. C 73, 044603 (2006) R.O.Sayer, K.H.Guber, L.C.Leal, N.M.Larson, T.Rauscher R-matrix analysis of Cl neutron cross sections up to 1.2 MeV NUCLEAR REACTIONS Cl, 35,37Cl(n, X), E=0.02-1250 keV; analyzed σ. 35,37Cl deduced resonance energies, widths, neutron strength functions. Multilevel Reich-Moore R-matrix formalism, comparison with previous results.
doi: 10.1103/PhysRevC.73.044603
1999LE69 Nucl.Sci.Eng. 131, 230 (1999) L.C.Leal, H.Derrien, N.M.Larson, R.Q.Wright R-Matrix Analysis of 235U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range NUCLEAR REACTIONS 235U(n, X), E=0-2250 eV; analyzed fission, capture, transmission σ; deduced resonance parameters. R-matrix analysis.
doi: 10.13182/NSE99-A2031
1997BO46 Nucl.Sci.Eng. 127, 105 (1997) O.Bouland, H.Derrien, N.M.Larson, L.C.Leal R-Matrix Analysis of the 240Pu Neutron Cross Sections in the Thermal to 5700-eV Energy Range NUCLEAR REACTIONS 240Pu(n, X), E=0.02-5700 eV; analyzed transmission, fission, total σ; deduced parameters. R-matrix analysis.
doi: 10.13182/NSE127-105
1993PE03 Phys.Rev. C47, 1143 (1993) C.M.Perey, F.G.Perey, J.A.Harvey, N.W.Hill, N.M.Larson, R.L.Macklin, D.C.Larson 58Ni + n Transmission, Differential Elastic Scattering, and Capture Measurements and Analysis up to 813 keV NUCLEAR REACTIONS 58Ni(n, X), E ≤ 20 MeV; measured transmission. 58Ni(n, n), E=0.01-5 MeV; measured σ(θ). 58Ni(n, γ), E=0.0026-2.5 MeV; measured capture σ(E). 59Ni deduced resonances, Γn, (gΓnΓγ/Γ), J, π.
doi: 10.1103/PhysRevC.47.1143
1992DE15 Ann.Nucl.Energy 19, 393 (1992) G.de Saussure, N.M.Larson, J.A.Harvey, N.W.Hill Multilevel Resonance Analysis of 59Co Neutron Transmission Measurements NUCLEAR REACTIONS 59Co(n, X), E=0.002-100 keV; analyzed transmission data; deduced total, thermal capture σ. 60Co deduced resonance parameters. Multi-level analysis.
doi: 10.1016/0306-4549(92)90033-8
1989DE37 Nucl.Sci.Eng. 103, 109 (1989) G.de Saussure, L.C.Leal, R.B.Perez, N.M.Larson, M.S.Moore A New Resonance Region Evaluation of Neutron Cross Sections for 235U NUCLEAR REACTIONS 235U(n, F), (n, γ), E ≤ 110 eV; calculated fission, capture σ(E).
1989MO21 Nucl.Phys. A502, 443c (1989) M.S.Moore, L.C.Leal, G.de Saussure, R.B.Perez, N.M.Larson Resonance Structure in the Fission of (235U + n) NUCLEAR REACTIONS 235U(n, F), (n, γ), (n, n), E=low, resonance; analyzed data. R-matrix, Pattenden-Postma constraints.
doi: 10.1016/0375-9474(89)90681-7
1987CO23 Nucl.Phys. A469, 480 (1987) G.P.Coddens, M.Salah, J.A.Harvey, N.W.Hill, N.M.Larson Resonance Structure of 33S + n from Transmission Measurements NUCLEAR REACTIONS 33S(n, n), E=0.010-2 MeV; measured σ(E). 34S deduced resonances, J, π, Γn, Γα, s-, p-wave strength function. Spherical optical model.
doi: 10.1016/0375-9474(87)90034-0
1987DE09 Nucl.Sci.Eng. 96, 58 (1987) H.Derrien, N.M.Larson, G.de Saussure, R.B.Perez R-Matrix Analysis of the 241Pu Cross Sections up to 100 eV NUCLEAR REACTIONS 241Pu(n, F), (n, n), (n, γ), E ≤ 100 eV; analyzed total, fission σ(E). 242Pu deduced neutron resonance parameters. R-matrix analysis.
doi: 10.13182/NSE87-A16365
1986LA34 Radiat.Eff. 96, 251 (1986) Uncertainty Propagation from Raw Data to Final Results NUCLEAR REACTIONS Fe, Ni(n, n), (n, n'), (n, γ), E=2-80 MeV; calculated σ(E); deduced uncertainty propagation.
doi: 10.1080/00337578608211746
1986PE03 Nucl.Sci.Eng. 93, 31 (1986) R.B.Perez, G.de Saussure, N.M.Larson, R.L.R.Macklin Multilevel Analysis of the Low-Energy 239Pu Cross Sections NUCLEAR REACTIONS 239Pu(n, γ), (n, F), E ≤ 30 eV; analyzed σ(E). 240Pu deduced resonances, Γγ, Γn, fission widths.
doi: 10.13182/NSE83-A17414
1983JO07 Phys.Rev. C27, 1913 (1983) C.H.Johnson, N.M.Larson, C.Mahaux, R.R.Winters Calculation of the Energy-Averaged Scattering Function from High Resolution Low-Energy Neutron Scattering Data NUCLEAR REACTIONS 32S(n, n), E ≈ 0.2-0.9 MeV; calculated σ(compound nucleus), σ(shape elastic) vs E. Optical model scattering function, energy averaging, p-wave neutrons.
doi: 10.1103/PhysRevC.27.1913
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