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NSR database version of April 24, 2024.

Search: Author = Y.Danon

Found 64 matches.

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2023FR01      Ann.Nucl.Energy 181, 109475 (2023)

D.Fritz, Y.Danon, M.Rapp, T.H.Trumbull, M.Zerkle, J.Holmes, C.W.Chapman, G.Arbanas, J.M.Brown, K.Ramic, X.Hu, S.Singh, A.Ney, P.Brain, K.Cook, B.Wang

Total thermal neutron cross section measurements of yttrium hydride from 0.0005 - 3 eV

NUCLEAR REACTIONS 89Y, H(n, X), E=0.0005 - 3 eV; measured reaction products, En, In; deduced total σ and uncertainties. Comparison with ENDF/B-VIII.0library. The RPI LINAC facility.

doi: 10.1016/j.anucene.2022.109475
Citations: PlumX Metrics


2023LE13      Eur.Phys.J. N 9, 34 (2023)

A.M.Lewis, A.D.Carlson, D.L.Smith, D.P.Barry, R.C.Block, S.Croft, Y.Danon, M.Drosg, M.W.Herman, D.Neudecker, N.Otuka, H .Sjostrand, V.Sobes

Templates of expected measurement uncertainties for total neutron cross-section observables

doi: 10.1051/epjn/2023018
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2023LE14      Eur.Phys.J. N 9, 33 (2023)

A.M.Lewis, D.Neudecker, A.D.Carlson, D.L.Smith, I.Thompson, A.Wallner, D.P.Barry, L.A.Bernstein, R.C.Block, S.Croft, Y.Danon, M.Drosg, R.C.Haight, M.W.Herman, H.Y.Lee, N.Otuka, H.Sjostrand, V.Sobes

Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables

doi: 10.1051/epjn/2023015
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2023NE01      Nucl.Instrum.Methods Phys.Res. A1048, 167930 (2023)

A.Ney, Y.Danon, M.L.Zerkle, P.Brain, D.Fritz, G.Siemers, S.Singh

A detection system for accurate (α, n) neutron counting measurements of low-rate (α, n) neutron sources

doi: 10.1016/j.nima.2022.167930
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2022BL01      Nucl.Sci.Eng. 196, 121 (2022)

E.Blain, Y.Danon, D.P.Barry, B.E.Epping, A.Youmans, M.J.Rapp, A.M.Daskalakis, R.C.Block

Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV

NUCLEAR REACTIONS 63,65Cu, Cu(n, n), E=0.5-20 MeV; measured reaction products, En, In; deduced relative σ(E). Comparison with ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0 libraries. Rensselaer Polytechnic Institute.

doi: 10.1080/00295639.2021.1961542
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2022KO12      Phys. Rev. Res. 4, 021001 (2022)

K.Kolos, V.Sobes, R.Vogt, C.E.Romano, M.S.Smith, L.A.Bernstein, D.A.Brown, M.T.Burkey, Y.Danon, M.A.Elsawi, B.L.Goldblum, L.H.Heilbronn, S.L.Hogle, J.Hutchinson, B.Loer, E.A.McCutchan, M.R.Mumpower, E.M.O'Brien, C.Percher, P.N.Peplowski, J.J.Ressler, N.Schunck, N.W.Thompson, A.S.Voyles, W.Wieselquist, M.Zerkle

Current nuclear data needs for applications

doi: 10.1103/PhysRevResearch.4.021001
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2022MO02      Ann.Nucl.Energy 165, 108647 (2022)

K.S.Mohindroo, Y.Danon, E.Blain, M.Devlin, K.J.Kelly

Quasi-differential neutron induced neutron emissions from 235U, and 239Pu

NUCLEAR REACTIONS C, 235U, 239Pu(N, X)1NN, E=0.82-20 MeV; measured reaction products, En, In; deduced neutron emission spectrum. Comparison with ENDF/B-VIII.0, JEFF-3.3, and JENDL-4.0 evaluated libraries. The Los Alamos Neutron Science Center.

doi: 10.1016/j.anucene.2021.108647
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2021BL05      Nucl.Sci.Eng. 195, 679 (2021)

R.C.Block, J.A.Burke, D.P.Barry, M.J.Rapp, S.Singh, Y.Danon

Neutron Transmission and Capture Measurements of 133Cs from 600 to 2000 eV

NUCLEAR REACTIONS 133Cs(n, X), (n, γ), E=600-2000 eV; measured reaction products, En, In, Eγ, Iγ; deduced capture yields, transmissions, resonance parameters. SAMMY Bayesian analysis code.

doi: 10.1080/00295639.2021.1877989
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14709.


2020BR01      Nucl.Sci.Eng. 194, 221 (2020)

J.M.Brown, R.C.Block, A.Youmans, H.Choun, A.Ney, E.Blain, D.P.Barry, M.J.Rapp, Y.Danon

Validation of Unresolved Neutron Resonance Parameters Using a Thick-Sample Transmission Measurement

NUCLEAR REACTIONS 181Ta, 238U(n, X), E<200 keV; measured reaction products, En, In; deduced transmission, average resonance parameters. Comparison with JEFF-3.3 and ENDF/B-VIII.0 libraries.

doi: 10.1080/00295639.2019.1688087
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14686.


2019BL03      Nucl.Sci.Eng. 193, 269 (2019)

R.C.Block, J.A.Burke, D.P.Barry, N.J.Drindak, G.Leinweber, K.E.Remley, R.V.Ballad, M.J.Rapp, Y.Danon

Neutron Transmission and Capture Measurements of 133Cs from 0.01 to 600 eV

NUCLEAR REACTIONS 133Cs(n, X), (n, γ), E=0.01-600 eV; measured reaction products, En, In; deduced yields, resonance parameters, σ, resonance integrals.

doi: 10.1080/00295639.2018.1520526
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14528.


2019RA19      Nucl.Sci.Eng. 193, 903 (2019)

M.J.Rapp, D.P.Barry, G.Leinweber, R.C.Block, B.E.Epping, T.H.Trumbull, Y.Danon

Tantalum, Titanium, and Zirconium Neutron Total Cross-Section Measurements from 0.4 to 25 MeV

NUCLEAR REACTIONS Ta, Ti, Zr(n, X), E=0.4-25 MeV; measured reaction products, En, In; deduced σ. Comparison with ENDF/B-VIII.0, JEFF-3.3 and JENDL-4.0 libraries.

doi: 10.1080/00295639.2019.1570750
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14576.


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
Citations: PlumX Metrics


2018CA08      Nucl.Data Sheets 148, 254 (2018)

R.Capote, A.Trkov, M.Sin, M.T.Pigni, V.G.Pronyaev, J.Balibrea, D.Bernard, D.Cano-Ott, Y.Danon, A.Daskalakis, T.Goricanec, M.W.Herman, B.Kiedrowski, S.Kopecky, E.Mendoza, D.Neudecker, L.Leal, G.Noguere, P.Schillebeeckx, I.Sirakov, E.S.Soukhovitskii, I.Stetcu, P.Talou

IAEA CIELO Evaluation of Neutron-induced Reactions on 235U and 238U Targets

NUCLEAR REACTIONS 235,238U(n, X), E<20 MeV; analyzed available data; calculated σ, σ(θ), σ(θ, E).

doi: 10.1016/j.nds.2018.02.005
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2018CH12      Nucl.Data Sheets 148, 189 (2018)

M.B.Chadwick, R.Capote, A.Trkov, M.W.Herman, D.A.Brown, G.M.Hale, A.C.Kahler, P.Talou, A.J.Plompen, P.Schillebeeckx, M.T.Pigni, L.Leal, Y.Danon, A.D.Carlson, P.Romain, B.Morillon, E.Bauge, F.-J.Hambsch, S.Kopecky, G.Giorginis, T.Kawano, J.Lestone, D.Neudecker, M.Rising, M.Paris, G.P.A.Nobre, R.Arcilla, O.Cabellos, I.Hill, E.Dupont, A.J.Koning, D.Cano-Ott, E.Mendoza, J.Balibrea, C.Paradela, I.Duran, J.Qian, Z.Ge, T.Liu, L.Hanlin, X.Ruan, W.Haicheng, M.Sin, G.Noguere, D.Bernard, R.Jacqmin, O.Bouland, C.De Saint Jean, V.G.Pronyaev, A.V.Ignatyuk, K.Yokoyama, M.Ishikawa, T.Fukahori, N.Iwamoto, O.Iwamoto, S.Kunieda, C.R.Lubitz, M.Salvatores, G.Palmiotti, I.Kodeli, B.Kiedrowski, D.Roubtsov, I.Thompson, S.Quaglioni, H.I.Kim, Y.O.Lee, U.Fischer, S.Simakov, M.Dunn, K.Guber, J.I.Marquez Damian, F.Cantargi, I.Sirakov, N.Otuka, A.Daskalakis, B.J.McDermott, S.C.van der Marck

CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen

NUCLEAR REACTIONS 1H, 16O, 56Fe, 235,238U, 239Pu(n, X), E<20 MeV; analyzed available data; calculated σ, σ(θ), σ(θ, E).

doi: 10.1016/j.nds.2018.02.003
Citations: PlumX Metrics


2018HE06      Nucl.Data Sheets 148, 214 (2018)

M.Herman, A.Trkov, R.Capote, G.P.A.Nobre, D.A.Brown, R.Arcilla, Y.Danon, A.Plompen, S.F.Mughabghab, Q.Jing, G.Zhigang, L.Tingjin, L.Hanlin, R.Xichao, L.Leal, B.V.Carlson, T.Kawano, M.Sin, S.P.Simakov, K.Guber

Evaluation of Neutron Reactions on Iron Isotopes for CIELO and ENDF/B-VIII.0

NUCLEAR REACTIONS 56Fe(n, X), E<20 MeV; analyzed available data; calculated σ, σ(θ), σ(θ, E).

doi: 10.1016/j.nds.2018.02.004
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2018RA28      Ann.Nucl.Energy 120, 778 (2018)

K.Ramic, C.Wendorff, Y.Cheng, A.I.Kolesnikov, D.L.Abernathy, L.Daemen, G.Arbanas, L.Leal, Y.Danon, L.Liu

Thermal scattering law of (C2H4)n: Integrating experimental data with DFT calculations

NUCLEAR REACTIONS C, H(n, n), E thermal; measured reaction products, En, In; deduced σ(θ, E). Comparison with ENDF/B-VII.1 library.

doi: 10.1016/j.anucene.2018.06.029
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14508.


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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14676.


2017BL01      Prog.Nucl.Energy 94, 126 (2017)

R.C.Block, M.C.Bishop, D.P.Barry, G.Leinweber, R.V.Ballad, J.A.Burke, M.J.Rapp, Y.Danon, A.Youmans, N.J.Drindak, G.N.Kim, Y.-R.Kang, M.W.Lee, S.Landsberger

Neutron transmission and capture measurements and analysis of Dy from 0.01 to 550 eV

NUCLEAR REACTIONS Dy, 154Dy(n, X), (n, γ), E<550 eV; measured reaction products, TOF, En, In, Eγ, Iγ; deduced capture yields, transmission, resonance parameters and integrals.

doi: 10.1016/j.pnucene.2016.09.019
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14470.


2017BL07      Phys.Rev. C 95, 064615 (2017)

E.Blain, A.Daskalakis, R.C.Block, Y.Danon

Measurement of prompt fission neutron spectrum for spontaneous fission of 252Cf using γ multiplicity tagging

RADIOACTIVITY 252Cf(SF); measured prompt fission neutron spectrum (PFNS) using the multiple γ-tagging method, energy of the neutrons by the time-of-flight (ToF) method at Rensselaer Polytechnic Institute. Comparison with previous experimental results. Simulations using MCNP-POLIMI code.

doi: 10.1103/PhysRevC.95.064615
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14477.


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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14518.


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
Citations: PlumX Metrics


2017EP02      Prog.Nucl.Energy 99, 59 (2017)

B.E.Epping, G.Leinweber, D.P.Barry, M.J.Rapp, R.C.Block, T.J.Donovan, Y.Danon, S.Landsberger

Rhenium resonance parameters from neutron capture and transmission measurements in the energy range 0.01 eV to 1 keV

NUCLEAR REACTIONS Re(n, X), (n, γ), E=0.00001-1 keV; measured reaction products, En, In. 185,187Re; deduced transmission and capture yields, resonance parameters, resonance integrals, thermal σ, level densities. Comparison with ENDF/B-VII.1 evaluated nuclear data library. SAMMY fit.

doi: 10.1016/j.pnucene.2017.04.015
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14475.


2017MC04      Phys.Rev. C 96, 014607 (2017)

B.J.McDermott, E.Blain, A.Daskalakis, N.Thompson, A.Youmans, H.J.Choun, W.Steinberger, Y.Danon, D.P.Barry, R.C.Block, B.E.Epping, G.Leinweber, M.R.Rapp

181Ta (n, γ) cross section and average resonance parameter measurements in the unresolved resonance region from 24 to 1180 keV using a filtered-beam technique

NUCLEAR REACTIONS 181Ta(n, γ), E=24-1180 keV; measured neutrons by TOF spectra, capture yields and σ(E) using an array of four Deuterated Benzene (C6D6) detectors at the Gaerttner Linear Accelerator Center of Rensselaer Polytechnic Institute. Comparison with previous experimental data, and evaluated libraries JEFF-3.2, JENDL-4.0, and ENDF/B-VII.1.

doi: 10.1103/PhysRevC.96.014607
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14473.


2017SH50      Eur.Phys.J. A 53, 203 (2017); Erratum Eur.Phys.J. A 53, 235 (2017)

S.G.Shin, Y.U.Kye, W.Namkung, M.H.Cho, Y.-R.Kang, M.W.Lee, G.N.Kim, T.-I.Ro, Y.Danon, D.Williams, G.Leinweber, R.C.Block, D.P.Barry, M.J.Rapp

Neutron capture measurements and resonance parameters of dysprosium

NUCLEAR REACTIONS Dy, 161,162,163,164Dy(n, γ), E=10-1000 eV; measured Eγ, Iγ, energies of neutron resonances using NaI(Tl) multiplicity detector divided into 16 optically isolated segments at Gaerttner LINAC Center of Rensselaer Polytechnic Institute; deduced resonance parameters, Γn, Γγ, capture resonance integrals, level densities, cumulative radiation. Comparison with results in ENDF/B-VII.1 evaluation, and with Porter-Thomas distribution.

doi: 10.1140/epja/i2017-12402-7
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14514.


2016BA01      Prog.Nucl.Energy 86, 11 (2016)

D.P.Barry, M.J.Rapp, R.C.Block, B.E.Epping, G.Leinweber, Y.Danon, A.Daskalakis, E.Blain, B.McDermott

236U resonance parameters at 5.467 eV from neutron transmission measurements using thin liquid samples

NUCLEAR REACTIONS 236U(n, X), E<100 eV; measured reaction products, En, In, TOF; deduced resonance parameters and widths, resonance integrals, total σ. Comparison with ENDF/B-VII.1, JEFF-3.2, JENDL-4.0 evaluated nuclear libraries.

doi: 10.1016/j.pnucene.2015.10.001
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14674.


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
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14421.


2015KA14      Nucl.Sci.Eng. 180, 86 (2015)

Y.-R.Kang, M.W.Lee, G.N.Kim, T.-I.Ro, Y.Danon, D.Williams, G.Leinweber, R.C.Block, D.P.Barry, M.J.Rapp

Neutron Capture Measurements and Resonance Parameters of Gadolinium

NUCLEAR REACTIONS 155,156,157,158,160Gd(n, γ), E<20 MeV; measured reaction products, Eγ, Iγ; deduced σ, yields, resonance parameters and integrals. Comparison with experimental data, ENDF/B-VII.0 library.

doi: 10.13182/NSE14-80
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14343.


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
Citations: PlumX Metrics


2014BL08      Nucl.Data Sheets 119, 209 (2014)

E.Blain, A.Daskalakis, Y.Danon

Measurement of Fission Neutron Spectrum and Multiplicity using a Gamma Tag Double Time-of-flight Setup

NUCLEAR REACTIONS 252Cf(n, F), E=0.01-0.5, 3-20 MeV; measured prompt fission En, In vs time using ToF; deduced unnormalized neutron spectrum vs energy. Compared with other data and ENDF/B-VII.1.

doi: 10.1016/j.nds.2014.08.058
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2014CA15      Nucl.Data Sheets 118, 26 (2014)

R.Capote, A.Trkov, M.Sin, M.Herman, A.Daskalakis, Y.Danon

Physics of Neutron Interactions with 238U: New Developments and Challenges

NUCLEAR REACTIONS 238U(n, x), E=0.01-20 MeV; calculated σ to different discrete states and to continuum. 238U(n, n), E=0-3.5 MeV; calculated average scattering angle. 238U(n, n), E=650 keV; calculated σ(θ). EMPIRE code; calculations compared to data and some reactions also to evaluated libraries.

doi: 10.1016/j.nds.2014.04.003
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2014CH24      Nucl.Data Sheets 118, 1 (2014)

M.B.Chadwick, E.Dupont, E.Bauge, A.Blokhin, O.Bouland, D.A.Brown, R.Capote, A.Carlson, Y.Danon, C.De Saint Jean, M.Dunn, U.Fischer, R.A.Forrest, S.C.Frankle, T.Fukahori, Z.Ge, S.M.Grimes, G.M.Hale, M.Herman, A.Ignatyuk, M.Ishikawa, N.Iwamoto, O.Iwamoto, M.Jandel, R.Jacqmin, T.Kawano, S.Kunieda, A.Kahler, B.Kiedrowski, I.Kodeli, A.J.Koning, L.Leal, Y.O.Lee, J.P.Lestone, C.Lubitz, M.MacInnes, D.McNabb, R.McKnight, M.Moxon, S.Mughabghab, G.Noguere, G.Palmiotti, A.Plompen, B.Pritychenko, V.Pronyaev, D.Rochman, P.Romain, D.Roubtsov, P.Schillebeeckx, M.Salvatores, S.Simakov, E.Sh.Soukhovitskii, J.C.Sublet, P.Talou, I.Thompson, A.Trkov, R.Vogt, S.van der Marck

The CIELO Collaboration: Neutron Reactions on 1H, 16O, 56Fe, 235, 238U, and 239Pu

COMPILATION 1H, 16O, 56Fe, 235,238U, 239Pu(n, x), E≈0-20 MeV; analyzed available data on σ, neutron multiplicity, criticality using ENDF/B-VII.1, JENDL-4.0, JEFF-3.1, ROSFOND 2010, CENDL-3.1, EAF-2010 evaluated nuclear libraries, Atlas of Neutron Resonances, Neutron Cross Section Standards evaluations; deduced recommendations for CIELO library, parameters, Maxwellian-averaged, thermal, californium σ, Westcott factors, resonance integrals. Compared with available data.

doi: 10.1016/j.nds.2014.04.002
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2014DA09      Nucl.Data Sheets 118, 179 (2014)

R.Dagan, B.Becker, Y.Danon, F.Gunsing, S.Kopecky, C.Lampoudis, O.Litaize, M.Moxon, P.Schillebeeckx

Impact of the Doppler Broadened Double Differential Cross Section on Observed Resonance Profiles

NUCLEAR REACTIONS 183W(n, γ), E≈45-50 eV;238U(n, γ), E=0.00001-5 eV; calculated Doppler broadening effect on resonance capture yields.

doi: 10.1016/j.nds.2014.04.031
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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
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2014DU08      Nucl.Data Sheets 120, 264 (2014)

E.Dupont, M.B.Chadwick, Y.Danon, C.De Saint Jean, M.Dunn, U.Fischer, R.A.Forrest, T.Fukahori, Z.Ge, H.Harada, M.Herman, M.Igashira, A.Ignatyuk, M.Ishikawa, O.Iwamoto, R.Jacqmin, A.C.Kahler, T.Kawano, A.J.Koning, L.Leal, Y.O.Lee, R.McKnight, D.McNabb, R.W.Mills, G.Palmiotti, A.Plompen, M.Salvatores, P.Schillebeeckx

Working Party on International Nuclear Data Evaluation Cooperation (WPEC)

doi: 10.1016/j.nds.2014.07.063
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2014KA38      Nucl.Data Sheets 119, 162 (2014)

Y.R.Kang, M.W.Lee, T.I.Ro, G.N.Kim, Y.Danon, D.Williams

Neutron Capture Measurements and Resonance Analysis of Dysprosium

NUCLEAR REACTIONS Dy, 161,162,163,164Dy(n, γ), E=10-1000 eV;measured Eγ, Iγ, γγ-coin using large-volume NaI(Tl) divided into 16 optically isolated segments; deduced capture yield, resonance parameters; calculated yields using SAMMY code. Compared with ENDF/B-VII.1 and JENDL-4.0.

doi: 10.1016/j.nds.2014.08.045
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2014LE07      Ann.Nucl.Energy 69, 74 (2014)

G.Leinweber, D.P.Barry, J.A.Burke, M.J.Rapp, R.C.Block, Y.Danon, J.A.Geuther, F.J.Saglime III

Europium resonance parameters from neutron capture and transmission measurements in the energy range 0.01-200 eV

NUCLEAR REACTIONS 151,153Eu(n, γ), (n, X), E=0.01-200 eV; measured reaction products, En, In, Eγ, Iγ; deduced resonance parameters, transmission and capture yields, resonance integrals. Comparison with ENDF/B-VII.1 library.

doi: 10.1016/j.anucene.2014.01.041
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14382.


2013BE02      Phys.Rev. C 87, 014617 (2013)

B.Becker, P.Talou, T.Kawano, Y.Danon, I.Stetcu

Monte Carlo Hauser-Feshbach predictions of prompt fission γ rays: Application to nth+235U, nth+239Pu, and 252Cf(sf)

NUCLEAR REACTIONS 235U, 239Pu(n, F), E=thermal; calculated ratio of neutron emission for light and heavy fragments as function of heavy fragment mass, neutron emission probability as function of excitation energy and different spin values of 146Ba, average initial fragment spin and energy, average and total neutron multiplicity, average prompt fission neutron spectrum, average center-of-mass energy of prompt fission neutrons, average Eγ and γ multiplicity, prompt fission γ spectrum and multiplicity. Monte Carlo Hauser-Feshbach model. Comparison with experimental data, and with other model calculations.

RADIOACTIVITY 252Cf(SF); calculated average center-of-mass energy of prompt fission neutrons, average prompt fission neutron and γ spectra, average Eγ, and multiplicity, total Eγ, average prompt fission γ multiplicity, γ multiplicity distribution. Monte Carlo Hauser-Feshbach model. Comparison with experimental data, and with other model calculations.

doi: 10.1103/PhysRevC.87.014617
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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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14349.


2012SC17      Nucl.Data Sheets 113, 3054 (2012)

P.Schillebeeckx, B.Becker, Y.Danon, K.Guber, H.Harada, J.Heyse, A.R.Junghans, S.Kopecky, C.Massimi, M.C.Moxon, N.Otuka, I.Sirakov, K.Volev

Determination of Resonance Parameters and their Covariances from Neutron Induced Reaction Cross Section Data

doi: 10.1016/j.nds.2012.11.005
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2012TH03      Nucl.Instrum.Methods Phys.Res. A673, 16 (2012)

J.T.Thompson, T.Kelley, E.Blain, R.C.Haight, J.M.O'Donnell, Y.Danon

Measurement of (n, α) reactions on 147Sm and 149Sm using a lead slowing-down spectrometer

NUCLEAR REACTIONS 147,149Sm(n, α), E=0.0001-10 keV; measured reaction products, Eα, Iα, Eγ, Iγ; deduced thermal σ. Comparison with previous measurements, ENDF/B-VII evaluated nuclear library.

doi: 10.1016/j.nima.2012.01.005
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14319.


2011CH57      Nucl.Data Sheets 112, 2887 (2011)

M.B.Chadwick, M.Herman, P.Oblozinsky, M.E.Dunn, Y.Danon, A.C.Kahler, D.L.Smith, B.Pritychenko, G.Arbanas, R.Arcilla, R.Brewer, D.A.Brown, R.Capote, A.D.Carlson, Y.S.Cho, H.Derrien, K.Guber, G.M.Hale, S.Hoblit, S.Holloway, T.D.Johnson, T.Kawano, B.C.Kiedrowski, H.Kim, S.Kunieda, N.M.Larson, L.Leal, J.P.Lestone, R.C.Little, E.A.McCutchan, R.E.MacFarlane, M.MacInnes, C.M.Mattoon, R.D.McKnight, S.F.Mughabghab, G.P.A.Nobre, G.Palmiotti, A.Palumbo, M.T.Pigni, V.G.Pronyaev, R.O.Sayer, A.A.Sonzogni, N.C.Summers, P.Talou, I.J.Thompson, A.Trkov, R.L.Vogt, S.C.van der Marck, A.Wallner, M.C.White, D.Wiarda, P.G.Young

ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay 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, 7,9Be, 10,11B, C, 14,15N, 16,17O, 19F, 22,23Na, 24,25,26Mg, 27Al, 28,29,30Si, 31P, 32,33,34,36S, 35,37Cl, 36,38,40Ar, 39,40,41K, 40,42,43,44,46,48Ca, 45Sc, 46,47,48,49,50Ti, 50,51V, 50,52,53,54Cr, 55Mn, 54,56,57,58Fe, 58,59Co, 58,59,60,61,62,64Ni, 63,65Cu, 65,66,67,68,70Zn, 69,71Ga, 70,72,73,74,76Ge, 74,75As, 74,76,77,78,79,80,82Se, 79,81Br, 78,80,82,83,84,85,86Kr, 85,86,87Rb, 84,86,87,88,89,90Sr, 89,90,91Y, 90,91,92,93,94,95,96Zr, 93,94,95Nb, 92,94,95,96,97,98,99,100Mo, 99Tc, 96,98,99,100,101,102,103,104,105,106Ru, 103,105Rh, 102,104,105,106,107,108,110Pd, 107,109,110,111Ag, 106,108,110,111,112,113,114,115,116Cd, 113,115In, 112,113,114,115,116,117,118,119,120,122,123,124,125,126Sn, 121,123,124,125,126Sb, 120,122,123,124,125,126,127,128,129,130,132Te, 127,129,130,131,135I, 123,124,126,128,129,130,131,132,133,134,135,136Xe, 133,134,135,136,137Cs, 130,132,133,134,135,136,137,138,140Ba, 138,139,140La, 136,138,139,140,141,142,143,144Ce, 141,142,143Pr, 142,143,144,145,146,147,148,150Nd, 147,148,149,151Pm, 144,147,148,149,150,151,152,153,154Sm, 151,152,153,154,155,156,157Eu, 152,153,154,155,156,157,158,160Gd, 159,160Tb, 156,158,160,161,162,163,164Dy, 165,166Ho, 162,164,166,167,168,170Er, 168,169,170Tm, 175,176Lu, 174,176,177,178,179,180Hf, 180,181,182Ta, 180,182,183,184,186W, 185,187Re, 191,193Ir, 197Au, 196,198,199,200,201,202,204Hg, 203,205Tl, 204,206,207,208Pb, 209Bi, 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, 236,237,238,239,240,241,242,243,244,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,249,250Bk, 246,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), E=30 keV; calculated Maxwellian-averaged σ using ENDF/B-VII.1 evaluated neutron library. Comparison with ENDF/B-VII.0 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, 236,237,238,239,240,241,242,243,244,246Pu, 240,241,242,243,244Am, 240,241,242,243,244,245,246,247,248,249,250Cm, 245,246,247,249,250Bk, 246,248,249,250,251,252,253,254Cf, 251,252,253,254,255Es, 255Fm(n, γ), (n, F), E=thermal; calculated thermal σ. Comparison with ENDF/B-VII.0, JENDL-4.0 and Atlas of Neutron Resonances values.

doi: 10.1016/j.nds.2011.11.002
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23170.


2011DA19      J.Korean Phys.Soc. 59, 983s (2011)

R.Dagan, B.Becker, Y.Danon, M.Rapp, D.Barry, G.Lohnert

Modelling Resonance Dependent Angular Distribution via DBRC in Monte Carlo Codes

NUCLEAR REACTIONS 232Th(n, n'), E≈1 MeV; measured thin, thick target En, In(θ=140.80); calculated unnormalized neutron energy spectra using standard and DBRC (Doppler broadened rejection corrections) MCNP.

doi: 10.3938/jkps.59.983
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2011DA20      J.Korean Phys.Soc. 59, 1649s (2011)

Y.Danon, R.Block, J.Thompson, C.Romano

Fission Physics and Cross Section Measurements with a Lead Slowing down Spectrometer

NUCLEAR REACTIONS 235U, 239Pu(n, F), E=thermal, 0.1 eV-2 keV; measured fission fragments E; deduced preneutron fission fragment yields vs TKE and mass, σ. 147,149Sm(n, α), E=0.01-1.E5 eV; measured reaction products; deduced σ. Compared to other data, ENDF/B-VII.0, JENDL-3.2. Measurements using LSDS (Lead Slowing Down Spectrometer).

doi: 10.3938/jkps.59.1649
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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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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14311.


2011TA15      Phys.Rev. C 83, 064612 (2011)

P.Talou, B.Becker, T.Kawano, M.B.Chadwick, Y.Danon

Advanced Monte Carlo modeling of prompt fission neutrons for thermal and fast neutron-induced fission reactions on 239Pu

NUCLEAR REACTIONS 239Pu(n, F), E=thermal, 0.5 MeV; calculated yield of fission fragments, width of the TKE distribution as function of fragment mass, Primary fission fragment yields as functions of mass, TKE, temperature ratio parameter, prompt fission neutron spectrum, multiplicity and center-of-mass energy. Monte Carlo approach to the evaporation of the excited fission fragments. Comparison with experimental and evaluated data.

doi: 10.1103/PhysRevC.83.064612
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2010RO04      Phys.Rev. C 81, 014607 (2010)

C.Romano, Y.Danon, R.Block, J.Thompson, E.Blain, E.Bond

Fission fragment mass and energy distributions as a function of incident neutron energy measured in a lead slowing-down spectrometer

NUCLEAR REACTIONS 235U(n, F), E=0.1-1 keV; measured fission fragments, fission σ, yield, TKE trends and fission mode ratio trends in resonance region, pre- and post-neutron emission mass distributions in lead-slowing down spectrometer (LSDS). 252Cf(SF); used as a reference. Comparisons with ENDF/B-VII.0.

doi: 10.1103/PhysRevC.81.014607
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14259.


2009DA01      Nucl.Sci.Eng. 161, 321 (2009)

Y.Danon, R.C.Block, M.J.Rapp, F.J.Saglime, G.Leinweber, D.P.Barry, N.J.Drindak, J.G.Hoole

Beryllium and Graphite High-Accuracy Total Cross-Section Measurements in the Energy Range from 24 to 900 keV

NUCLEAR REACTIONS Be, C, Fe(n, X), E=24-950 keV; measured total cross sections. Compared results to evaluated databases.

doi: 10.13182/NSE161-321
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14233.


2009HA29      Nucl.Technology 168, 576 (2009)

B.Han, B.Bednarz, Y.Danon, R.Block, X.G.Xu

Evaluation of Nuclear Activation of Tungsten Plates for Future Modeling of a Medical Accelerator

doi: 10.13182/NT09-A9246
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2009RO21      J.Korean Phys.Soc. 55, 1389 (2009)

T.Ro, Y.Danon, E.Liu, D.P.Barry, R.Dagan

Measurements of the Neutron Scattering Spectrum from 238U and Comparison of the Results with a Calculation at the 36.68-eV Resonance

NUCLEAR REACTIONS 238U(n, n'), E=5-120 eV; measured En, In; deduced 36.68-eV resonance, scattering probability, σ. Comparison with ENDF/B-VII.0 library.

doi: 10.3938/jkps.55.1389
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2006BA19      Nucl.Sci.Eng. 153, 8 (2006)

D.P.Barry, M.J.Trbovich, Y.Danon, R.C.Block, R.E.Slovacek, G.Leinweber, J.A.Burke, N.J.Drindak

Neutron Transmission and Capture Measurements and Resonance Parameter Analysis of Neodymium from 1 to 500 eV

NUCLEAR REACTIONS Nd(n, n'X), E=1-500 eV; measured transmission spectra. Nd(n, γ), E=1-500 eV; measured capture yields. 143,144,145,146,148,150Nd deduced resonance parameters. Comparison with previous results.

doi: 10.13182/NSE06-A2590
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14093.


2006DR08      Nucl.Sci.Eng. 154, 294 (2006)

N.J.Drindak, J.A.Burke, G.Leinweber, J.A.Helm, J.G.Hoole, R.C.Block, Y.Danon, R.E.Slovacek, B.E.Moretti, C.J.Werner, M.E.Overberg, S.A.Kolda, M.J.Trbovich, D.P.Barry

Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Niobium

NUCLEAR REACTIONS Nb(n, X), (n, γ), E ≈ 0-500 eV; measured transmission and capture σ; deduced resonance parameters.

doi: 10.13182/NSE06-A2634
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14112.


2006GE02      Phys.Rev.Lett. 96, 054803 (2006)

J.Geuther, Y.Danon, F.Saglime

Nuclear Reactions Induced by a Pyroelectric Accelerator

NUCLEAR REACTIONS 2H(d, n), E ≈ 20-200 keV; measured neutron spectra, yields. Deuteron beam from electrostatic field of pyroelectric crystal in a deuterated atmosphere.

doi: 10.1103/PhysRevLett.96.054803
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2006LE35      Nucl.Sci.Eng. 154, 261 (2006)

G.Leinweber, D.P.Barry, M.J.Trbovich, J.A.Burke, N.J.Drindak, H.D.Knox, R.V.Ballad, R.C.Block, Y.Danon, L.I.Severnyak

Neutron Capture and Total Cross-Section Measurements and Resonance Parameters of Gadolinium

NUCLEAR REACTIONS 155,157Gd(n, X), (n, γ), E ≈ 0-300 eV; measured transmission and capture σ; deduced resonance parameters. Comparison with previous results.

doi: 10.13182/NSE05-64
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2006RO22      Nucl.Instrum.Methods Phys.Res. A562, 771 (2006)

C.Romano, Y.Danon, R.C.Haight, S.A.Wender, D.J.Vieira, E.M.Bond, R.S.Rundberg, J.B.Wilhelmy, J.M.O'Donnell, A.F.Michaudon, T.A.Bredeweg, D.Rochman, T.Granier, T.Ethvignot

Measurements of (n, α) cross-section of small samples using a lead-slowing-down-spectrometer

NUCLEAR REACTIONS 6Li(n, α), E ≈ 0.1-10000 eV; measured Eα, σ(E). Lead-slowing-down spectrometer.

doi: 10.1016/j.nima.2006.02.052
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14105.


2006RO28      Nucl.Instrum.Methods Phys.Res. A564, 400 (2006)

D.Rochman, R.C.Haight, J.M.O'Donnell, S.A.Wender, D.J.Vieira, E.M.Bond, T.A.Bredeweg, J.B.Wilhelmy, T.Granier, T.Ethvignot, M.Petit, Y.Danon, C.Romano

Cross-section measurements for 239Pu(n, f) and 6Li(n, α) with a lead slowing-down spectrometer

NUCLEAR REACTIONS 239Pu(n, F), E < 100 keV; measured fission σ. 6Li(n, α), E < 10 keV; measured σ. Lead slowing-down spectrometer.

doi: 10.1016/j.nima.2006.03.032
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14108.


2005DA20      Nucl.Instrum.Methods Phys.Res. A544, 659 (2005)

Y.Danon, R.C.Block

Minimizing the statistical error in capture cross-section measurements

NUCLEAR REACTIONS 147Sm(n, γ), E ≈ resonance; measured capture σ. Minimization of statistical error discussed.

doi: 10.1016/j.nima.2004.12.034
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2005RO30      Nucl.Instrum.Methods Phys.Res. A550, 397 (2005)

D.Rochman, R.C.Haight, J.M.O'Donnell, A.Michaudon, S.A.Wender, D.J.Vieira, E.M.Bond, T.A.Bredeweg, A.Kronenberg, J.B.Wilhelmy, T.Ethvignot, T.Granier, M.Petit, Y.Danon

Characteristics of a lead slowing-down spectrometer coupled to the LANSCE accelerator

NUCLEAR REACTIONS 235U, 239Pu(n, F), E < 100 keV; measured fission σ. Lead slowing-down spectrometer.

doi: 10.1016/j.nima.2005.04.075
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2003WA24      Nucl.Instrum.Methods Phys.Res. A513, 585 (2003)

S.Wang, M.Lubert, Y.Danon, N.C.Francis, R.C.Block, F.Becvar, M.Krticka

The RPI multiplicity detector response to γ-ray cascades following neutron capture in 149Sm and 150Sm

NUCLEAR REACTIONS 149,150Sm(n, γ), E not given; calculated γ-ray multiplicity distributions, detector response. Statistical model, comparison with data.

doi: 10.1016/S0168-9002(03)01941-7
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2000LE01      Nucl.Sci.Eng. 134, 50 (2000)

G.Leinweber, J.Burke, C.R.Lubitz, H.D.Knox, N.J.Drindak, R.C.Block, R.E.Slovacek, C.J.Werner, N.C.Francis, Y.Danon, B.E.Moretti

Neutron Capture and Total Cross-Section Measurements and Resonance Parameter Analysis of Zirconium up to 2.5 keV

NUCLEAR REACTIONS Zr(n, X), (n, γ), E < 2.5 keV; measured capture and transmission σ. 91,96Zr deduced resonance parameters.

doi: 10.13182/NSE00-A2099
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset13744.


1998DA26      Nucl.Sci.Eng. 128, 61 (1998)

Y.Danon, C.J.Werner, G.Youk, R.C.Block, R.E.Slovacek, N.C.Francis, J.A.Burke, N.J.Drindak, F.Feiner, J.A.Helm

Neutron Total Cross-Section Measurements and Resonance Parameter Analysis of Holmium, Thulium, and Erbium from 0.001 to 20 eV

NUCLEAR REACTIONS Ho, Th, Er, 166,167Er(n, X), E=0.001-20 eV; measured transmission spectra; deduced total σ, resonance parameters. Corrections for paramagnetic scattering discussed.

doi: 10.13182/NSE98-A1945
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset13725.


1996DA42      Nucl.Sci.Eng. 124, 482 (1996)

Y.Danon, M.S.Moore, P.E.Koehler, P.E.Littleton, G.G.Miller, M.A.Ott, L.J.Rowton, W.A.Taylor, J.B.Wilhelmy, M.A.Yates, A.D.Carlson, N.W.Hill, R.Harper, R.Hilko

Fission Cross-Section Measurements of the Odd-Odd Isotopes 232Pa, 238Np, and 236Np

NUCLEAR REACTIONS, ICPND 232Th(p, n), (p, 3n), E=threshold-20 MeV; 232Th(d, n), (d, 2n), E=threshold-20 MeV; measured residuals production σ(E). 232Pa, 238,236Np(n, F), E < 100 keV; measured fission σ(E). 237Np deduced resonances, fission width, 2gΓn.

doi: 10.13182/NSE96-A17926
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset13602.


1994BL14      Proc.Intern.Conf.Nuclear Data for Science and Technology, Gatlinburg, Tennesse, 9-13 May, 1994, J.K.Dickens, Ed., American Nuclear Society, Vol.1, p.81 (1994)

R.C.Block, Y.Danon, R.E.Slovacek, C.J.Werner, G.Youk, J.A.Burke, N.J.Drindak, F.Feiner, J.A.Helm, J.C.Sayres, K.W.Seemann

Neutron time-of-flight measurements at the Rensselaer Linac

NUCLEAR REACTIONS 197Au(n, n), 197Au(n, γ), E=4.89-78.3 eV; measured products, Eγ, Iγ; deduced resonance parameters. Data were imported from EXFOR entry 14086.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset14086.


1994DA41      Proc.Intern.Conf.Nuclear Data for Science and Technology, Gatlinburg, Tennesse, 9-13 May, 1994, J.K.Dickens, Ed., American Nuclear Society, Vol.1, p.245 (1994)

Y.Danon, M.S.Moore, P.E.Koehler, R.W.Lougheed, R.W.Hoff, N.W.Hill

Measurement and analysis of the neutron-induced fission cross section s of 247Cm, 250Cf and 254Es

NUCLEAR REACTIONS 247Cm(n, n), 247Cm(n, f), 250Cf(n, f), 254Es(n, f), E=-8.8E-4 eV-9.8 keV; measured products; deduced σ, σ(E), resonance parameters. Data were imported from EXFOR entry 13646.

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset13646.


1991DA19      Nucl.Sci.Eng. 109, 341 (1991)

Y.Danon, R.E.Slovacek, R.C.Block, R.W.Lougheed, R.W.Hoff, M.S.Moore

Fission Cross-Section Measurements of 247Cm, 254Es, and 250Cf from 0.1 eV to 80 keV

NUCLEAR REACTIONS 247Cm, 254Es, 250Cf(n, F), E ≤ 80 keV; measured fission σ(E). 248Cm deduced resonance widths.

doi: 10.13182/NSE91-A23859
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset13197.


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