NSR Query Results


Output year order : Descending
Format : Normal

NSR database version of May 24, 2024.

Search: Author = M.E.Dunn

Found 9 matches.

Back to query form



2015AR02      Nucl.Data Sheets 123, 51 (2015)

G.Arbanas, M.L.Williams, L.C.Leal, M.E.Dunn, B.A.Khuwaileh, C.Wang, H.Abdel-Khalik

Advancing Inverse Sensitivity/Uncertainty Methods for Nuclear Fuel Cycle Applications

doi: 10.1016/j.nds.2014.12.009
Citations: PlumX Metrics


2014AR06      Nucl.Data Sheets 118, 374 (2014)

G.Arbanas, M.E.Dunn, M.L.Williams

Inverse Sensitivity/Uncertainty Methods Development for Nuclear Fuel Cycle Applications

doi: 10.1016/j.nds.2014.04.084
Citations: PlumX Metrics


2014PI04      Nucl.Data Sheets 118, 147 (2014)

M.T.Pigni, L.C.Leal, M.E.Dunn, K.H.Guber, A.Trkov, G.Zerovnik, F.Emiliani, S.Kopecky, C.Lampoudis, P.Schillebeeckx, P.Siegler

Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Region

NUCLEAR REACTIONS 182,183,184,186W(n, x), E≈thermal-4 keV; calculated capture σ, scattering σ, transmission coefficients using R-matrix code SAMMY; deduced resonance parameters using 2010 and 2012 Geel data.

doi: 10.1016/j.nds.2014.04.022
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.


2011DU25      J.Korean Phys.Soc. 59, 1207s (2011)

M.E.Dunn, H.Derrien, L.C.Leal, C.Gil, D.Kim

Resonance Region Nuclear Data Analysis to Support Advanced Fuel Cycle Development

COMPILATION 240Pu(n, γ), 244Cm(n, n), E=0.0005 eV-20 MeV; calculated, evaluated σ, resonance covariance data using ENDF/B-VII.0, JEFF-3.1.1, JENDL-3.3.

doi: 10.3938/jkps.59.1207
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


2008WI12      Nucl.Data Sheets 109, 2791 (2008)

D.Wiarda, G.Arbanas, L.Leal, M.E.Dunn

Recent Advances with the AMPX Covariance Processing Capabilities in PUFF-IV

doi: 10.1016/j.nds.2008.11.011
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


2004DU20      Nucl.Sci.Eng. 148, 30 (2004)

M.E.Dunn, L.C.Leal

Calculating Probability Tables for the Unresolved-Resonance Region Using Monte Carlo Methods

NUCLEAR REACTIONS 235U(n, X), (n, γ), (n, F), (n, n'), E=2.25-25.0 keV; calculated average σ in unresolved-resonance region. Monte-Carlo approach.

doi: 10.13182/NSE04-A2438
Citations: PlumX Metrics


Back to query form