NSR Query Results
Output year order : Descending NSR database version of April 11, 2024. Search: Author = P.Siegler Found 15 matches. 2014GU14 Nucl.Data Sheets 119, 113 (2014) K.Guber, S.Kopecky, P.Schillebeeckx, K.Kauwenberghs, P.Siegler Neutron-induced Cross Section Measurements of Calcium NUCLEAR REACTIONS Ca(n, n'), E=1-300 keV; measured neutrons; deduced neutron transmission; calculated neutron transmission using ENDF/B-VII.1 resonance parameters. Compared with ENDF/VII-1. Ca(n, γ), E=14-160 keV; measured reaction products; deduced σ; calculated σ using ENDF/B-VII.1 resonance parameters.
doi: 10.1016/j.nds.2014.08.032
2014PI04 Nucl.Data Sheets 118, 147 (2014) M.T.Pigni, L.C.Leal, M.E.Dunn, K.H.Guber, A.Trkov, G.Zerovnik, F.Emiliani, S.Kopecky, C.Lampoudis, P.Schillebeeckx, P.Siegler Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Region NUCLEAR REACTIONS 182,183,184,186W(n, x), E≈thermal-4 keV; calculated capture σ, scattering σ, transmission coefficients using R-matrix code SAMMY; deduced resonance parameters using 2010 and 2012 Geel data.
doi: 10.1016/j.nds.2014.04.022
2014SC14 Nucl.Data Sheets 119, 94 (2014) P.Schillebeeckx, B.Becker, R.Capote, F.Emiliani, K.Guber, J.Heyse, K.Kauwenberghs, S.Kopecky, C.Lampoudis, C.Massimi, W.Mondelaers, M.Moxon, G.Noguere, A.J.M.Plompen, V.Pronyaev, P.Siegler, I.Sirakov, A.Trkov, K.Volev, G.Zerovnik Evaluation of Neutron Resonance Cross Section Data at GELINA
doi: 10.1016/j.nds.2014.08.027
2014SO08 Nucl.Data Sheets 118, 155 (2014) V.Sobes, L.C.Leal, K.Guber, B.Forget, S.Kopecky, P.Schillebeeckx, P.Siegler New Resolved Resonance Region Evaluation for 63, 65Cu for Nuclear Criticality Safety Program NUCLEAR REACTIONS 63,65Cu(n, γ), E=reactor; calculated σ using Reich-Moore version of R-matrix theory; deduced new resonance regions.
doi: 10.1016/j.nds.2014.04.024
2013VO01 Nucl.Instrum.Methods Phys.Res. B300, 11 (2013) K.Volev, A.Borella, S.Kopecky, C.Lampoudis, C.Massimi, A.Moens, M.Moxon, P.Schillebeeckx, P.Siegler, I.Sirakov, A.Trkov, R.Wynants Evaluation of resonance parameters for neutron induced reactions in cadmium NUCLEAR REACTIONS 106,108,110,111,112,113,114,116Cd, Cd(n, γ), (n, X), E thermal; analysed available data from GELINA time of flight facility; deduced σ, resonance parameters. Comparison with JEFF-3.1.2, JENDL 4.0, ENDF/B-VII.1 evaluated libraries.
doi: 10.1016/j.nimb.2013.01.030
2011AN23 J.Korean Phys.Soc. 59, 1597s (2011) S.Andriamonje, M.Calviani, Y.Kadi, R.Losito, V.Vlachoudis, E.Berthoumieux, F.Gunsing, A.Giganon, Y.Giomataris, C.Guerrero, R.Sarmento, P.Schillebeeckx, P.Siegler A Transparent Detector for n_TOF Neutron Beam Monitoring
doi: 10.3938/jkps.59.1597
2011LA19 J.Korean Phys.Soc. 59, 1785s (2011) C.Lampoudis, S.Kopecky, A.Plompen, P.Schillebeeckx, P.Siegler, F.Gunsing, C.Sage, O.Bouland Transmission and Capture Measurements for 241Am at GELINA NUCLEAR REACTIONS 241Am(n, n'), (n, γ), E=0.1-100 eV; measured En, In, Eγ, Iγ; deduced capture yields, transmission; calculated capture yields, transmission using R-matrix.
doi: 10.3938/jkps.59.1785
2011LA20 J.Korean Phys.Soc. 59, 1860s (2011) C.Lampoudis, S.Kopecky, P.Schillebeeckx, P.Siegler, K.Guber Neutron Total and Capture Cross Section of Tungsten Isotopes NUCLEAR REACTIONS 182,183,184,186W(n, γ), (n, X), E=0.9-1.5 keV; measured In, Eγ, Iγ using 6Li glass and C6D6 detectors; deduced transmission factor, capture yield. Compared with JEFF-3.1.
doi: 10.3938/jkps.59.1860
2009KO14 Nucl.Instrum.Methods Phys.Res. B267, 2345 (2009) S.Kopecky, I.Ivanov, M.Moxon, P.Schillebeeckx, P.Siegler, I.Sirakov The total cross section and resonance parameters for the 0.178 eV resonance of 113Cd NUCLEAR REACTIONS 113Cd(n, γ), E not given; measured neutron transmission; deduced resonance parameters.
doi: 10.1016/j.nimb.2009.04.010
2009NO12 Nucl.Phys. A831, 106 (2009) G.Noguere, E.Rich, C.De Saint Jean, O.Litaize, P.Siegler, V.Avrigeanu Average neutron parameters for hafnium NUCLEAR REACTIONS 174,176,177,178,179,180Hf(n, γ), E=0.002-50 keV; measured transmission and capture σ at the GELINA white neutron source facility; deduced resonance parameters using Reich-Moore interpretation and the REFIT code. Comparison with data.
doi: 10.1016/j.nuclphysa.2009.08.011
2008NO08 Nucl.Sci.Eng. 160, 108 (2008) G.Noguere, D.Bernard, C.De Saint Jean, B.Iooss, F.Gunsing, K.Kobayashi, S.F.Mughabghab, P.Siegler Assessment and Propagation of the 237Np Nuclear Data Uncertainties in Integral Calculations by Monte Carlo Techniques NUCLEAR REACTIONS 237Np(n, γ), (n, X), E<10 eV; analyzed available data; deduced level energies, J, π, resonance parameters, thermal neutron σ, resonance integrals.
doi: 10.13182/NSE160-108
2007BO24 Phys.Rev. C 76, 014605 (2007); Erratum Phys.Rev. C 76, 019904 (2007) A.Borella, F.Gunsing, M.Moxon, P.Schillebeeckx, P.Siegler High-resolution neutron transmission and capture measurements of the nucleus 206Pb NUCLEAR REACTIONS 206Pb(n, n'), (n, γ), E=1-620 keV; measured En, Eγ, and yields. Deduced resonance parameters.
doi: 10.1103/PhysRevC.76.014605
2006NO12 Phys.Rev. C 74, 054602 (2006) G.Noguere, O.Bouland, A.Brusegan, P.Schillebeeckx, P.Siegler, A.Lepretre, N.Herault, G.Rudolf Neutron capture and total cross sections of 127I and 129I NUCLEAR REACTIONS 127,129I(n, γ), (n, X), E=0.0005-100 keV; measured transmission and capture σ; deduced resonance parameters.
doi: 10.1103/PhysRevC.74.054602
2000HA52 Nucl.Phys. A679, 3 (2000) F.-J.Hambsch, F.Vives, P.Siegler, S.Oberstedt Study of the 237Np(n, f)-Reaction at MeV Neutron Energies NUCLEAR REACTIONS 237Np(n, F), E=0.3-5.5 MeV; measured fission σ, fragments kinetic energy and mass distributions. Comparison with multimodal random-neck rupture model.
doi: 10.1016/S0375-9474(00)00338-9
1995SI21 Nucl.Phys. A594, 45 (1995) P.Siegler, F.-J.Hambsch, S.Oberstedt, J.P.Theobald Fission Modes in the Compound Nucleus 238Np NUCLEAR REACTIONS 237Np(n, F), E=5.5 MeV; analyzed fission fragment total kinetic energy vs mass, dissymmetry distributions. 238Np deduced fission modes characteristics. Multi-model random neck-rupture model, potential energy calculations.
doi: 10.1016/0375-9474(95)00364-7
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