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NSR database version of April 26, 2024.

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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, ^{28,29,30,31,32}Si, ³¹P, ^{32,33,34,35,36}S, ^35,36,37Cl, ^{36,37,38,39,40,41}Ar, ^39,40,41K, ^{40,41,42,43,44,45,46,47,48}Ca, ⁴⁵Sc, ^{46,47,48,49,50}Ti, ^49,50,51V, ^{50,51,52,53,54}Cr, ^54,55Mn, ^{54,55,56,57,58}Fe, ^58,59Co, ^{58,59,60,61,62,63,64}Ni, ^63,64,65Cu, ^{64,65,66,67,68,69,70}Zn, ^69,70,71Ga, ^{70,71,72,73,74,75,76}Ge, ^73,74,75As, ^{74,75,76,77,78,79,80,81,82}Se, ^79,80,81Br, ^{78,79,80,81,82,83,84,85,86}Kr, ^85,86,87Rb, ^{84,85,86,87,88,89,90}Sr, ^89,90,91Y, ^{90,91,92,93,94,95,96}Zr, ^93,94,95Nb, ^{92,93,94,95,96,97,98,99,100}Mo, ^98,99Tc, ^{96,97,98,99,100,101,102,103,104,105,106}Ru, ^103,104,105Rh, ^{102,103,104,105,106,107,108,109,110}Pd, ^{107,108,109,110,111,112,113,114,115,116,117,118}Ag, ^{106,107,108,109,110,111,112,113,114,115,116}Cd, ^113,114,115In, ^{112,113,114,115,116,117,118,119,120,121,122,123,124,125,126}Sn, ^{121,122,123,124,125,126}Sb, ^{120,121,122,123,124,125,126,127,128,129,130,121,132}Te, ^{127,128,129,130,131,132,133,134,135}I, ^{123,124,125,126,127,128,129,130,131,132,133,134,135,136}Xe, ^{133,134,135,136,137}Cs, ^{130,131,132,133,134,135,136,137,138,139,140}Ba, ^138,139,140La, ^{136,137,138,139,140,141,142,143,144}Ce, ^141,142,143Pr, ^{142,143,144,145,146,147,148,149,150}Nd, ^{143,144,145,146,147,148,149,151}Pm, ^{144,145,146,147,148,149,150,151,152,153,154}Sm, ^{151,152,153,154,155,156,157}Eu, ^{152,153,154,155,156,157,158,159,160}Gd, ^{158,159,160,161}Tb, ^{154,155,156,157,158,159,160,161,162,163,164}Dy, ^165,166Ho, ^{162,163,164,165,166,167,168,170,170}Er, ^{168,169,170,171}Tm, ^{168,169,170,171,172,173,174,175,176}Yb, ^175,176Lu, ^{174,175,176,177,178,179,180,181,182}Hf, ^180,181,182Ta, ^{180,181,182,183,184,185,186}W, ^185,186,187Re, ^{184,185,186,187,188,189,190,191,192}Os, ^191,192,193Ir, ^{190,191,192,193,194,195,196,197,198}Pt, ¹⁹⁷Au, ^{196,197,198,199,200,201,202,203,204}Hg, ^203,204,205Tl, ^{204,205,206,207,208,209,210}Pb, ^209,210Bi, ^208,209,210Po, ^{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, ^{236,237,238,239,240,241,242,243,244,245,246}Pu, ^{240,241,242,243,244}Am, ^{240,241,242,243,244,245,246,247,248,249,250}Cm, ^{245,246,247,248,249,250}Bk, ^{246,247,248,249,250,251,252,253,254}Cf, ^{251,252,253,254,255}Es, ²⁵⁵Fm(n, γ), E=30 keV; calculated Maxwellian-averaged σ using ENDF/B-VIII.0 evaluated neutron library. Comparison with ENDF/B-VII.1 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, ^{236,237,238,239,240,241,242,243,244,245,246}Pu, ^{240,241,242,243,244}Am, ^{240,241,242,243,244,245,246,247,248,249,250}Cm, ^{245,246,247,248,249,250}Bk, ^{246,247,248,249,250,251,252,253,254}Cf, ^{251,252,253,254,255}Es, ²⁵⁵Fm(n, γ), (n, F), E=thermal; calculated thermal σ. Comparison with ENDF/B-VII.1, JENDL-4.0u+ and Atlas of Neutron Resonances values.

doi: 10.1016/j.nds.2018.02.001
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