NSR Query Results
Output year order : Descending NSR database version of April 27, 2024. Search: Author = R.M.Bahran Found 8 matches. 2018RE12 Ann.Nucl.Energy 122, 23 (2018) K.E.Remley, G.Leinweber, D.P.Barry, R.C.Block, M.J.Rapp, Y.Danon, R.M.Bahran Transmission measurements and resonance parameter analysis for Mo-98 and Mo-100 NUCLEAR REACTIONS 98,100Mo(n, X), E<100 keV; measured reaction products, En, In; deduced resonance parameters, level density. Comparison with ENDF/B-VIII.0 library.
doi: 10.1016/j.anucene.2018.08.006
2017DA19 Nucl.Sci.Eng. 187, 291 (2017) Y.Danon, D.Williams, R.Bahran, E.Blain, B.McDermott, D.Barry, G.Leinweber, R.Block, M.Rapp Simultaneous Measurement of 235U Fission and Capture Cross Sections From 0.01 eV to 3 keV Using a Gamma Multiplicity Detector NUCLEAR REACTIONS 235U(n, γ), (n, F), E=0.00001-3 keV; measured reaction products, En, In, Eγ, Iγ; deduced σ. Comparison with ENDF/B-VII.1 and JENDL-4.0 evaluated nuclear data libraries.
doi: 10.1080/00295639.2017.1312937
2017DA24 Ann.Nucl.Energy 110, 603 (2017) A.M.Daskalakis, E.J.Blain, B.J.McDermott, R.M.Bahran, Y.Danon, D.P.Barry, R.C.Block, M.J.Rapp, B.E.Epping, G.Leinweber Quasi-differential elastic and inelastic neutron scattering from iron in the MeV energy range NUCLEAR REACTIONS Fe(n, n), (n, n'), E<2 MeV; measured reaction products, En, In; deduced σ. Comparison with ENDF/B-VII.1, JEFF-3.2 and JENDL-4.0 libraries.
doi: 10.1016/j.anucene.2017.07.007
2015BA34 Phys.Rev. C 92, 024601 (2015) R.Bahran, D.Barry, R.Block, G.Leinweber, M.Rapp, A.Daskalakis, E.Blain, D.Williams, B.McDermott, L.Leal, Y.Danon Isotopic molybdenum total neutron cross section in the unresolved resonance region NUCLEAR REACTIONS 95,96,98,100Mo(n, γ), E=1-620 keV; measured neutron time-of-flight (TOF) transmission spectra, high-resolution total cross-section σ(E), strength functions, average resonance parameters in the unresolved energy region (URR) using Mid-Energy 6Li-glass Neutron Detector Array (MELINDA) at RPI Gaerttner LINAC Center. Hauser-Feshbach statistical model calculations using FITACS code. Comparison with ENDF/B-VII.1, JEFF 3.2, JENDL 4.0 evaluated library.
doi: 10.1103/PhysRevC.92.024601
2014BA33 Nucl.Data Sheets 119, 137 (2014) R.Bahran, D.Barry, G.Leinweber, M.Rapp, R.Block, A.Daskalakis, B.McDermott, S.Piela, E.Blain, Y.Danon Isotopic Mo Neutron Total Cross Section Measurements in the Energy Range 1 to 620 keV NUCLEAR REACTIONS 92,94,95,96,98,100Mo(n, γ), (n, x), E=1-620 keV; measured En, In, Eγ, Iγ; deduced σ, new resonances, resonance parameters using SAMMY R-matrix code fit. Compared with ENDF/B-VII.1.
doi: 10.1016/j.nds.2014.08.038
2014DA11 Ann.Nucl.Energy 73, 455 (2014) A.M.Daskalakis, R.M.Bahran, E.J.Blain, B.J.McDermott, S.Piela, Y.Danon, D.P.Barry, G.Leinweber, R.C.Block, M.J.Rapp, R.Capote, A.Trkov Quasi-differential neutron scattering from 238U from 0.5 to 20 MeV NUCLEAR REACTIONS 238U(n, n), E=0.5-20 MeV; measured reaction products, En, In; deduced σ(θ). MCNP calculations, comparison with ENDF/B-VII.1, ENDF/B-VI.8, JENDL-4.0, JEFF-3.1 libraries.
doi: 10.1016/j.anucene.2014.07.023
2012RA24 Nucl.Sci.Eng. 172, 268 (2012) M.J.Rapp, Y.Danon, F.J.Saglime, R.M.Bahran, D.G.Williams, G.Leinweber, D.P.Barry, R.C.Block Beryllium and Graphite Neutron Total Cross-Section Measurements from 0.4 to 20 MeV NUCLEAR REACTIONS Be, C(n, X), E=0.4-20 MeV; measured reaction products, TOF; deduced total neutron σ. Comparison with available data, Monte Carlo measurements and ENDF/B-VI.8, ENDF/B-VII.0, JEFF-3.1 and JENDL-4.0 evaluated libraries.
doi: 10.13182/NSE11-55
2011RA38 J.Korean Phys.Soc. 59, 1745s (2011) M.J.Rapp, Y.Danon, F.J.Saglime, R.Bahran, R.C.Block, G.Leinweber, D.P.Barry, J.G.Hoole Molybdenum and Zirconium Neutron Total Cross Section Measurements in the Energy Range 0.5 TO 20 MeV NUCLEAR REACTIONS Zr, Mo(n, X), E=0.5-20 MeV; measured thick target En, In; deduced total σ. Compared with ENDF/B-VI.8, ENDF/B/VII.0, JEFF-3.1, JENDL-3.3.
doi: 10.3938/jkps.59.1745
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