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NSR database version of April 27, 2024.

Search: Author = W.B.Wilson

Found 13 matches.

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2012HA06      Phys.Rev. C 85, 024617 (2012)

A.C.Hayes, H.R.Trellue, M.M.Nieto, W.B.Wilson

Antineutrino monitoring of burning mixed oxide plutonium fuels

RADIOACTIVITY ^235,238U, ^239,241Pu(SF); analyzed fission fraction, effective antineutrino detection cross section, and antineutrino signal as function of burn-up of LEU and MOX reactor and weapon grade fuels using Monteburns (MCNP+CINDER90) code. Relevance to nuclear accountability.

doi: 10.1103/PhysRevC.85.024617
Citations: PlumX Metrics

2009WI04      Prog.Nucl.Energy 51, 608 (2009)

W.B.Wilson, R.T.Perry, W.S.Charlton, T.A.Parish

Sources: A code for calculating (alpha, n), spontaneous fission, and delayed neutron sources and spectra

doi: 10.1016/j.pnucene.2008.11.007
Citations: PlumX Metrics

2008KA37      Phys.Rev. C 78, 054601 (2008)

T.Kawano, P.Moller, W.B.Wilson

Calculation of delayed-neutron energy spectra in a quasiparticle random-phase approximation-Hauser-Feshbach model

RADIOACTIVITY ⁸⁰Ge, ^{87,88,89,90,91,92}Br, ^{141,142,143,144,145,146,147,148}Cs, ¹⁴⁶Xe(β^-n); calculated Gamow-Teller strengths, delayed neutron energy spectra. QRPA and Hauser-Feshbach model.

doi: 10.1103/PhysRevC.78.054601
Citations: PlumX Metrics

2007YO07      Nucl.Data Sheets 108, 2589 (2007)

P.G.Young, M.B.Chadwick, R.E.MacFarlane, P.Talou, T.Kawano, D.G.Madland, W.B.Wilson, C.W.Wilkerson

Evaluation of Neutron Reactions for ENDF/B-VII:^232-241U and ²³⁹PU

NUCLEAR REACTIONS ^{232,233,234,235,236,237,239,240,241}U, ²³⁹Pu(n, X), E< 30 MeV; evaluated cross sections for ENDF/B-VII.

doi: 10.1016/j.nds.2007.11.002
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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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2006GI01      Nucl.Sci.Eng. 153, 33 (2006)

M.-L.Giacri-Mauborgne, D.Ridikas, M.B.Chadwick, P.G.Young, W.B.Wilson

Photonuclear Physics in Radiation Transport-III: Actinide Cross Sections and Spectra

NUCLEAR REACTIONS ^235,238U, ²³⁹Pu, ²³⁷Np(γ, n), (γ, 2n), (γ, F), E=5-20 MeV; calculated, analyzed photonuclear σ. ^235,238U, ²³⁹Pu, ²³⁷Np(γ, X), E=5-20 MeV; calculated, analyzed total photoabsorption σ.

doi: 10.13182/NSE06-A2592
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2006RI08      Nucl.Instrum.Methods Phys.Res. A562, 710 (2006)

D.Ridikas, M.-L.Giacri, M.B.Chadwick, J.-C.David, D.Dore, X.Ledoux, A.Van Lauwe, W.B.Wilson

Status of the photonuclear activation file: Reaction cross-sections, fission fragments and delayed neutrons

NUCLEAR REACTIONS ¹⁸¹Ta(γ, n), (γ, 2n), E=5-25 MeV; ²⁴¹Am(γ, n), (γ, 2n), (γ, F), E=5-20 MeV; analyzed σ. ²³⁵U(γ, F), E=15 MeV bremsstrahlung; analyzed fission fragment mass distribution.

doi: 10.1016/j.nima.2006.02.028
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2002WI17      Prog.Nucl.Energy 41, 71 (2002)

W.B.Wilson, T.R.England

Delayed Neutron Study Using ENDF/B-VI Basic Nuclear Data

NUCLEAR REACTIONS ^227,229,232Th, ²³¹Pa, ^{232,233,234,235,236,237,238}U, ^237,238Np, ^{238,239,240,241,242}Pu, ^241,242m,243Am, ^{242,243,244,245,246,248}Cm, ^249,251Cf, ²⁵⁴Es, ²⁵⁵Fm(n, F), E ≈ thermal-14 MeV; calculated delayed neutron production rates following fission.

RADIOACTIVITY ²³⁸U, ^244,246,248Cm, ^250,252Cf, ²⁵³Es, ^254,256Fm(SF); calculated delayed neutron production rates.

doi: 10.1016/S0149-1970(02)00006-9
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2002WI20      Prog.Nucl.Energy 41, 71 (2002)

W.B.Wilson, T.R.England

Delayed neutron study using ENDF/B-VI basic nuclear data

doi: 10.1016/S0149-1970(02)00006-9
Citations: PlumX Metrics

2001VA20      Nucl.Instrum.Methods Phys.Res. A463, 576 (2001)

K.A.Van Riper, S.G.Mashnik, W.B.Wilson

A Computer Study of Radionuclide Production in High Power Accelerators for Medical and Industrial Applications

NUCLEAR REACTIONS ^{131,132,134,136}Xe(p, X)¹³¹Cs, E ≈ 3-2000 MeV; ¹⁰⁰Mo(p, X)⁹⁵Zr/⁹⁵Nb, E ≈ 20-2000 MeV; O, F, Ne, ^20,21,22Ne, Na, Mg, ^24,25,26Mg, ²⁷Al(p, X)¹⁸F, E=1.7 GeV; calculated production σ.

doi: 10.1016/S0168-9002(01)00172-3
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2001WA23      Nucl.Instrum.Methods Phys.Res. A463, 634 (2001)

J.-S.Wan, Th.Schmidt, E.-J.Langrock, P.Vater, R.Brandt, J.Adam, V.Bradnova, V.P.Bamblevski, L.Gelovani, T.D.Gridnev, V.G.Kalinnikov, M.I.Krivopustov, B.A.Kulakov, A.N.Sosnin, V.P.Perelygin, V.S.Pronskikh, V.I.Stegailov, V.M.Tsupko-Sitnikov, G.Modolo, R.Odoj, P.-W.Phlippen, M.Zamani-Valassiadou, J.C.Adloff, M.Debeauvais, S.R.Hashemi-Nezhad, S.-L.Guo, L.Li, Y.-L.Wang, K.K.Dwivedi, I.V.Zhuk, S.F.Boulyga, E.M.Lomonosova, A.F.Kievitskaya, I.L.Rakhno, S.E.Chigrinov, W.B.Wilson

Transmutation of ¹²⁹I and ²³⁷Np using Spallation Neutrons Produced by 1.5, 3.7 and 7.4 GeV Protons

NUCLEAR REACTIONS ¹²⁹I, ²³⁷Np(n, γ), E=spectrum; measured transmutation rates. Comparison with model predictions.

doi: 10.1016/S0168-9002(01)00175-9
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1989YO11      Trans.Amer.Nucl.Soc. 60, 271 (1989)

P.G.Young, E.D.Arthur, M.Bozoian, T.R.England, G.M.Hale, R.J.LaBauve, R.C.Little, R.E.MacFarlane, D.G.Madland, R.T.Perry, W.B.Wilson

7. Transport data libraries for incident proton and neutron energies to 100 MeV

NUCLEAR REACTIONS ¹H, ⁹Be, C, O, ²⁷Al, Si, Fe, W, ²³⁸U(p, X), ¹H, ⁹Be, C, O, ²⁷Al, Si, Ca, Fe, W, ²³⁸U(n, X), E<100 MeV; analyzed available data; deduced σ for transport libraries.

1983EN03      Nucl.Sci.Eng. 85, 139 (1983)

T.R.England, W.B.Wilson, R.E.Schenter, F.M.Mann

Aggregate Delayed Neutron Intensities and Spectra using Augumented ENDF/B-V Precursor Data

RADIOACTIVITY A=79-150; calculated β-delayed neutron intensities, emission probabilities (P(n)), precursor fission yields. ^{88,89,90,91,92,93,94,95,96,97,98,99}Rb(β^-n); calculated T_1/2, neutron spectra. Aggregate summation method, ENDF/B-V precursor data.

doi: 10.13182/NSE83-A27422
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