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NSR database version of April 27, 2024.

Search: Author = M.E.Dunn

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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
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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
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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 ^{182,183,184,186}W(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
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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, ^{40,42,43,44,46,48}Ca, ⁴⁵Sc, ^{46,47,48,49,50}Ti, ^50,51V, ^50,52,53,54Cr, ⁵⁵Mn, ^54,56,57,58Fe, ^58,59Co, ^{58,59,60,61,62,64}Ni, ^63,65Cu, ^{65,66,67,68,70}Zn, ^69,71Ga, ^{70,72,73,74,76}Ge, ^74,75As, ^{74,76,77,78,79,80,82}Se, ^79,81Br, ^{78,80,82,83,84,85,86}Kr, ^85,86,87Rb, ^{84,86,87,88,89,90}Sr, ^89,90,91Y, ^{90,91,92,93,94,95,96}Zr, ^93,94,95Nb, ^{92,94,95,96,97,98,99,100}Mo, ⁹⁹Tc, ^{96,98,99,100,101,102,103,104,105,106}Ru, ^103,105Rh, ^{102,104,105,106,107,108,110}Pd, ^{107,109,110,111}Ag, ^{106,108,110,111,112,113,114,115,116}Cd, ^113,115In, ^{112,113,114,115,116,117,118,119,120,122,123,124,125,126}Sn, ^{121,123,124,125,126}Sb, ^{120,122,123,124,125,126,127,128,129,130,132}Te, ^{127,129,130,131,135}I, ^{123,124,126,128,129,130,131,132,133,134,135,136}Xe, ^{133,134,135,136,137}Cs, ^{130,132,133,134,135,136,137,138,140}Ba, ^138,139,140La, ^{136,138,139,140,141,142,143,144}Ce, ^141,142,143Pr, ^{142,143,144,145,146,147,148,150}Nd, ^{147,148,149,151}Pm, ^{144,147,148,149,150,151,152,153,154}Sm, ^{151,152,153,154,155,156,157}Eu, ^{152,153,154,155,156,157,158,160}Gd, ^159,160Tb, ^{156,158,160,161,162,163,164}Dy, ^165,166Ho, ^{162,164,166,167,168,170}Er, ^168,169,170Tm, ^175,176Lu, ^{174,176,177,178,179,180}Hf, ^180,181,182Ta, ^{180,182,183,184,186}W, ^185,187Re, ^191,193Ir, ¹⁹⁷Au, ^{196,198,199,200,201,202,204}Hg, ^203,205Tl, ^{204,206,207,208}Pb, ²⁰⁹Bi, ^{223,224,225,226}Ra, ^225,226,227Ac, ^{227,228,229,230,231,232,233,234}Th, ^{229,230,231,232,233}Pa, ^{230,231,232,233,234,235,236,237,238,239,240,241}U, ^{234,235,236,237,238,239}Np, ^{236,237,238,239,240,241,242,243,244,246}Pu, ^{240,241,242,243,244}Am, ^{240,241,242,243,244,245,246,247,248,249,250}Cm, ^{245,246,247,249,250}Bk, ^{246,248,249,250,251,252,253,254}Cf, ^{251,252,253,254,255}Es, 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 ^{227,228,229,230,231,232,233,234}Th, ^{229,230,231,232,233}Pa, ^{230,231,232,233,234,235,236,237,238,239,240,241}U, ^{234,235,236,237,238,239}Np, ^{236,237,238,239,240,241,242,243,244,246}Pu, ^{240,241,242,243,244}Am, ^{240,241,242,243,244,245,246,247,248,249,250}Cm, ^{245,246,247,249,250}Bk, ^{246,248,249,250,251,252,253,254}Cf, ^{251,252,253,254,255}Es, 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
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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
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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
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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
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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
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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
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