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NSR database version of May 21, 2024.

Search: Author = M.A.Descalle

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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
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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
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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
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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
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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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