NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = R.Q.Wright Found 2 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
1999LE69 Nucl.Sci.Eng. 131, 230 (1999) L.C.Leal, H.Derrien, N.M.Larson, R.Q.Wright R-Matrix Analysis of 235U Neutron Transmission and Cross-Section Measurements in the 0- to 2.25-keV Energy Range NUCLEAR REACTIONS 235U(n, X), E=0-2250 eV; analyzed fission, capture, transmission σ; deduced resonance parameters. R-matrix analysis.
doi: 10.13182/NSE99-A2031
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