NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = M.A.Descalle Found 5 matches. 2018BR05 Nucl.Data Sheets 148, 1 (2018) D.A.Brown, M.B.Chadwick, R.Capote, A.C.Kahler, A.Trkov, M.W.Herman, A.A.Sonzogni, Y.Danon, A.D.Carlson, M.Dunn, D.L.Smith, G.M.Hale, G.Arbanas, R.Arcilla, C.R.Bates, B.Beck, B.Becker, F.Brown, R.J.Casperson, J.Conlin, D.E.Cullen, M.-A.Descalle, R.Firestone, T.Gaines, K.H.Guber, A.I.Hawari, J.Holmes, T.D.Johnson, T.Kawano, B.C.Kiedrowski, A.J.Koning, S.Kopecky, L.Leal, J.P.Lestone, C.Lubitz, J.I.Marquez Damian, C.M.Mattoon, E.A.McCutchan, S.Mughabghab, P.Navratil, D.Neudecker, G.P.A.Nobre, G.Noguere, M.Paris, M.T.Pigni, A.J.Plompen, B.Pritychenko, V.G.Pronyaev, D.Roubtsov, D.Rochman, P.Romano, P.Schillebeeckx, S.Simakov, M.Sin, I.Sirakov, B.Sleaford, V.Sobes, E.S.Soukhovitskii, I.Stetcu, P.Talou, I.Thompson, S.van der Marck, L.Welser-Sherrill, D.Wiarda, M.White, J.L.Wormald, R.Q.Wright, M.Zerkle, G.Zerovnik, Y.Zhu ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering 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, 9Be, 10,11B, 12,13C, 14,15N, 16,17,18O, 19F, 20,21,22Ne, 22,23Na, 24,25,26Mg, 26,27Al, 28,29,30,31,32Si, 31P, 32,33,34,35,36S, 35,36,37Cl, 36,37,38,39,40,41Ar, 39,40,41K, 40,41,42,43,44,45,46,47,48Ca, 45Sc, 46,47,48,49,50Ti, 49,50,51V, 50,51,52,53,54Cr, 54,55Mn, 54,55,56,57,58Fe, 58,59Co, 58,59,60,61,62,63,64Ni, 63,64,65Cu, 64,65,66,67,68,69,70Zn, 69,70,71Ga, 70,71,72,73,74,75,76Ge, 73,74,75As, 74,75,76,77,78,79,80,81,82Se, 79,80,81Br, 78,79,80,81,82,83,84,85,86Kr, 85,86,87Rb, 84,85,86,87,88,89,90Sr, 89,90,91Y, 90,91,92,93,94,95,96Zr, 93,94,95Nb, 92,93,94,95,96,97,98,99,100Mo, 98,99Tc, 96,97,98,99,100,101,102,103,104,105,106Ru, 103,104,105Rh, 102,103,104,105,106,107,108,109,110Pd, 107,108,109,110,111,112,113,114,115,116,117,118Ag, 106,107,108,109,110,111,112,113,114,115,116Cd, 113,114,115In, 112,113,114,115,116,117,118,119,120,121,122,123,124,125,126Sn, 121,122,123,124,125,126Sb, 120,121,122,123,124,125,126,127,128,129,130,121,132Te, 127,128,129,130,131,132,133,134,135I, 123,124,125,126,127,128,129,130,131,132,133,134,135,136Xe, 133,134,135,136,137Cs, 130,131,132,133,134,135,136,137,138,139,140Ba, 138,139,140La, 136,137,138,139,140,141,142,143,144Ce, 141,142,143Pr, 142,143,144,145,146,147,148,149,150Nd, 143,144,145,146,147,148,149,151Pm, 144,145,146,147,148,149,150,151,152,153,154Sm, 151,152,153,154,155,156,157Eu, 152,153,154,155,156,157,158,159,160Gd, 158,159,160,161Tb, 154,155,156,157,158,159,160,161,162,163,164Dy, 165,166Ho, 162,163,164,165,166,167,168,170,170Er, 168,169,170,171Tm, 168,169,170,171,172,173,174,175,176Yb, 175,176Lu, 174,175,176,177,178,179,180,181,182Hf, 180,181,182Ta, 180,181,182,183,184,185,186W, 185,186,187Re, 184,185,186,187,188,189,190,191,192Os, 191,192,193Ir, 190,191,192,193,194,195,196,197,198Pt, 197Au, 196,197,198,199,200,201,202,203,204Hg, 203,204,205Tl, 204,205,206,207,208,209,210Pb, 209,210Bi, 208,209,210Po, 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, 236,237,238,239,240,241,242,243,244,245,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,248,249,250Bk, 246,247,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), E=30 keV; calculated Maxwellian-averaged σ using ENDF/B-VIII.0 evaluated neutron library. Comparison with ENDF/B-VII.1 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, 236,237,238,239,240,241,242,243,244,245,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,248,249,250Bk, 246,247,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), (n, F), E=thermal; calculated thermal σ. Comparison with ENDF/B-VII.1, JENDL-4.0u+ and Atlas of Neutron Resonances values.
doi: 10.1016/j.nds.2018.02.001
2012VO01 Phys.Rev. C 85, 024608 (2012) R.Vogt, J.Randrup, D.A.Brown, M.A.Descalle, W.E.Ormand Event-by-event evaluation of the prompt fission neutron spectrum from 239Pu(n, f) NUCLEAR REACTIONS 239Pu(n, F), E<20 MeV; analyzed chance fission probability, probability for pre-equilibrium neutron emission, fragment mass yields, total and average fragment kinetic energies, neutron multiplicity, prompt neutron spectra, neutron-neutron correlation coefficient contour plots. Event-by-event fission model FREYA with multichance fission and pre-equilibrium neutron emission. Comparison with ENDF-B/VII.0 evaluation.
doi: 10.1103/PhysRevC.85.024608
2011BR16 J.Korean Phys.Soc. 59, 1084s (2011) D.Brown, B.Beck, M.-A.Descalle, R.Hoffman, E.Ormand, P.Navratil, N.Summers, I.Thompson, R.Vogt, W.Younes, R.Barnowski Overview of the 2009 Release of the Evaluated Nuclear Data Library (ENDL2009) COMPILATION 27Al(n, γ), (n, X), E=1.E-8-20 MeV;27Al(n, 2n), E=10-20 MeV;181Ta, 187Re(n, γ), (n, x), E=1.E-11-20 MeV;181Ta, 187Re(n, 2n), E=5-20 MeV;76,77,78Kr, 122,123,124Xe(n, X), E=0-20 MeV; calculated, evaluated σ. TALYS code. ENDL2009 library, 585 transport-ready evaluations in neutron sub-library and 35 in charged-particle sub-libraries.
doi: 10.3938/jkps.59.1084
2005PR23 J.Appl.Phys. 97, 094908 (2005) J.Pruet, M.-A.Descalle, J.Hall, B.Pohl, S.G.Prussin Neutron and photon transport in seagoing cargo containers
doi: 10.1063/1.1887835
2004PR06 Nucl.Instrum.Methods Phys.Res. B222, 403 (2004) J.Pruet, J.Hall, M.-A.Descalle, S.Prussin Monte Carlo models for the production of β-delayed gamma-rays following fission of special nuclear materials NUCLEAR REACTIONS 235U, 239Pu(n, F), E=thermal; calculated β-delayed Eγ from fission product decay. Monte Carlo approach.
doi: 10.1016/j.nimb.2004.03.062
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