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NSR database version of May 30, 2024.

Search: Author = G.Noguere

Found 44 matches.

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2024GK01      Phys.Rev. C 109, 034612 (2024)

G.Gkatis, M.Diakaki, G.Noguere, M.Nyman, A.Oprea, C.Paradela, E.Pirovano, A.J.M.Plompen

Cross section measurements of neutron elastic and inelastic scattering on 54Fe

doi: 10.1103/PhysRevC.109.034612
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2021CH42      Ann.Nucl.Energy 163, 108553 (2021)

S.Chen, E.Vandermeersch, P.Tamagno, D.Bernard, G.Noguere, P.Blaise

Uncertainty propagation from n+56Fe nuclear reaction model parameters to neutron multiplication factor

NUCLEAR REACTIONS 56Fe(n, n), (n, n'), E<20 MeV; calculated propagation of the covariance matrix of continuum reaction model parameters; deduced uncertainties. Comparison with EXFOR, ENDF/B-VIII.0 and JEF-3.1.1 libraries.

doi: 10.1016/j.anucene.2021.108553
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2020BO18      Phys.Rev. C 102, 054608 (2020)

O.Bouland, G.Noguere

Reconciling surrogate-reaction probabilities and neutron-induced cross sections

NUCLEAR REACTIONS 240Pu(α, α')240Pu*, E*=4.6-8 MeV; calculated fission and γ probabilities as function of excitation energy of the compound system using AVXSF-LNG code with TALYS Jπ distributions, and compared with surrogate-reaction method (SRM) based estimates using JEFF-3.3 cross sections. 240Pu*,241Pu*,242Am*; calculated cumulative number of levels as a function of the excitation energy (<5 MeV) on top of the outer fission barrier using the combinatorial quasiparticle-vibrational-rotational level density method. 174Yb(3He, p)176Lu*, E*=6-7.5 MeV; calculated γ-ray emission probability for direct reaction as a function of excitation energy of the compound system using the AVXSF-LNG CODE with a uniform spin-parity entrance distribution, and compared with SRM-based calculations. 176Lu*; calculated width fluctuation correction factors, involved in the calculation of neutron-induced average cross sections of 175Lu, as a function of excitation energy (6.4-9.2 MeV) of 176Lu. 175Lu(n, γ), E=20-1000 keV; calculated radiative-capture σ(E) using the extended surrogate-reaction method (ESRM) transformation of the experimental γ-ray emission probability data set from 2012Bo08, and compared with evaluated and other experimental data. Discussed application of new ERSM as a technique to jointly analyze γ-ray probability and cross section data.

doi: 10.1103/PhysRevC.102.054608
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2020NO07      Phys.Rev. C 102, 015807 (2020)

G.Noguere, B.Geslot, A.Gruel, P.Leconte, L.Salamon, J.Heyse, S.Kopecky, C.Paradela, P.Schillebeeckx

Average neutron cross sections of 99Tc

NUCLEAR REACTIONS 99Tc(n, γ), E=0.003-150 keV; measured transmitted neutrons, E(n) by time-of-flight method using Li-glass detector at the GELINA-Geel facility; deduced total σ(E), capture σ(E), Maxwellian-averaged cross section (MACS) at kT=30 keV, s-wave average radiation widths, energies and parameters of 120 discrete neutron resonances from 5.59 to 1008.5 eV, J, π, neutron and γ widths. Comparison with theoretical calculations using TALYS code, and with previous experimental cross sections given in the EXFOR database.

doi: 10.1103/PhysRevC.102.015807
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23730.

2020PL02      Eur.Phys.J. A 56, 181 (2020)

A.J.M.Plompen, O.Cabellos, C.De Saint Jean, M.Fleming, A.Algora, M.Angelone, P.Archier, E.Bauge, O.Bersillon, A.Blokhin, F.Cantargi, A.Chebboubi, C.Diez, H.Duarte, E.Dupont, J.Dyrda, B.Erasmus, L.Fiorito, U.Fischer, D.Flammini, D.Foligno, M.R.Gilbert, J.R.Granada, W.Haeck, F.-J.Hambsch, P.Helgesson, S.Hilaire, I.Hill, M.Hursin, R.Ichou, R.Jacqmin, B.Jansky, C.Jouanne, M.A.Kellett, D.H.Kim, H.I.Kim, I.Kodeli, A.J.Koning, A.Yu.Konobeyev, S.Kopecky, B.Kos, A.Krasa, L.C.Leal, N.Leclaire, P.Leconte, Y.O.Lee, H.Leeb, O.Litaize, M.Majerle, J.I.Marquez Damian, F.Michel-Sendis, R.W.Mills, B.Morillon, G.Noguere, M.Pecchia, S.Pelloni, P.Pereslavtsev, R.J.Perry, D.Rochman, A.Rohrmoser, P.Romain, P.Romojaro, D.Roubtsov, P.Sauvan, P.Schillebeeckx, K.H.Schmidt, O.Serot, S.Simakov, I.Sirakov, H.Sjostrand, A.Stankovskiy, J.C.Sublet, P.Tamagno, A.Trkov, S.van der Marck, F.Alvarez-Velarde, R.Villari, T.C.Ware, K.Yokoyama, G.Zerovnik

The joint evaluated fission and fusion nuclear data library, JEFF-3.3

doi: 10.1140/epja/s10050-020-00141-9
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2019NO09      Phys.Rev. C 100, 065806 (2019)

G.Noguere, O.Bouland, J.Heyse, S.Kopecky, C.Paradela, P.Schillebeeckx, A.Ebran, O.Roig

s-wave average neutron resonance parameters of 175Lu + n

NUCLEAR REACTIONS 175Lu(n, γ), E=0.001-1 keV; measured neutron spectra using time-of-flight technique at the GELINA facility of JRC-Geel; deduced resonances, resonance parameters, energies, J, π, Γn, Γγ of 214 n-resonances up to 1 keV, average radiation width. Resonance parameters used the neutron resonance shape analysis technique and the Reich-Moore approximation of the R-matrix theory. Reviewed previous experimental and evaluated Lu(n, γ) data. 175Lu(n, γ), E=100 eV to 10 MeV; calculated shape-elastic and total σ(E) using the ECIS code, capture σ times the square root of the incident neutron energy using the TALYS code, and compared with available experimental data.

doi: 10.1103/PhysRevC.100.065806
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23728.

2019SA56      Nucl.Instrum.Methods Phys.Res. B446, 19 (2019)

L.Salamon, B.Geslot, J.Heyse, S.Kopecky, P.Leconte, G.Noguere, C.Paradela, P.Schillebeeckx, L.Snoj

107Ag and 109Ag resonance parameters for neutron induced reactions below 1 keV

NUCLEAR REACTIONS 107,109Ag(n, X), (n, γ), E<1 keV; measured reaction products, En, In, Eγ, Iγ; deduced neutron resonance parameters, resonance energy, neutron and radiation widths, resonance integrals, yields. Comparison with ENDF/B-VIII.0, JENDL-4.0 and JEFF-3.2 evaluated libraries.

doi: 10.1016/j.nimb.2019.03.012
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23533.

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
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2018CA07      Nucl.Data Sheets 148, 143 (2018), Erratum Nucl.Data Sheets 163, 280 (2020)

A.D.Carlson, V.G.Pronyaev, R.Capote, G.M.Hale, Z.-P.Chen, I.Duran, F.-J.Hambsch, S.Kunieda, W.Mannhart, B.Marcinkevicius, R.O.Nelson, D.Neudecker, G.Noguere, M.Paris, S.P.Simakov, P.Schillebeeckx, D.L.Smith, X.Tao, A.Trkov, A.Wallner, W.Wang

Evaluation of the Neutron Data Standards

NUCLEAR REACTIONS H, C(n, n), 6Li(n, t), 10B(n, αγ), 197Au(n, γ), 235,238U, 239Pu(n, F), 238U(n, γ), E<20 MeV; analyzed available data; deduced σ and Maxwellian spectrum averaged cross section for the 197Au(n, γ) σ at 30 keV, covariance matrices of the uncertainties.

RADIOACTIVITY 252Cf(SF); analyzed available data; deduced spontaneous fission neutron spectrum.

doi: 10.1016/j.nds.2018.02.002
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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
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2018DE09      Nucl.Data Sheets 148, 383 (2018)

C.De Saint Jean, P.Archier, E.Privas, G.Noguere, B.Habert, P.Tamagno

Evaluation of Neutron-induced Cross Sections and their Related Covariances with Physical Constraints

NUCLEAR REACTIONS 238U(n, X), 245Cm(n, F), 239Pu(n, γ), E<20 MeV; analyzed available data; deduced σ and covariance matrices.

doi: 10.1016/j.nds.2018.02.010
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2018NO04      Eur.Phys.J.Plus 133, 99 (2018)

G.Noguere, J.Tommasi, E.Privas, K.-H.Schmidt, D.Rochman

Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu

NUCLEAR REACTIONS 235,238U, 238,239,240,241Pu(n, F)143Nd/145Nd/146Nd/148Nd/150Nd, E<10 MeV; analyzed available data of the PROFIL experiments; calculated cumulative fission yields as a function of the incident neutron energy using GEF code.

doi: 10.1140/epjp/i2018-11926-y
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2017NO01      Ann.Nucl.Energy 104, 132 (2017)

G.Noguere, J.P.Scotta, C.De Saint Jean, P.Archier

Covariance matrices of the hydrogen neutron cross sections bound in light water for the JEFF-3.1.1 neutron library

NUCLEAR REACTIONS H, O(n, X), E<10 eV; calculated S(α, β) uncertainties using Monte-Carlo techniques.

doi: 10.1016/j.anucene.2017.01.044
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2015DE01      Nucl.Data Sheets 123, 178 (2015)

C.De Saint Jean, P.Archier, E.Privas, G.Noguere, O.Litaize, P.Leconte

Evaluation of Cross Section Uncertainties Using Physical Constraints: Focus on Integral Experiments

doi: 10.1016/j.nds.2014.12.031
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2015NO03      Phys.Rev. C 92, 014607 (2015)

G.Noguere, O.Bouland, S.Kopecky, C.Lampoudis, P.Schillebeeckx, A.Plompen, F.Gunsing, C.Sage, I.Sirakov

Partial-wave analysis of n + 241Am reaction cross sections in the resonance region

NUCLEAR REACTIONS 241Am(n, γ), E<150 eV; analyzed and evaluated time-of-flight cross section data from experiments carried out at the GELINA, LANSCE, ORELA and Saclay facilities with optical model calculations; deduced resonances, σ(E), widths and resonance parameters from resonance shape analysis of transmissions, capture yields, fission yields, neutron strength function, mean level spacing, average radiation width for s-wave resonances, neutron strength functions for higher partial waves together with channel and effective scattering radii. R-matrix analysis using the RFIT code. Comparison with calculations using the ECIS, TALYS and CONRAD computer codes.

doi: 10.1103/PhysRevC.92.014607
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Data from this article have been entered in the XUNDL database. For more information, click here.

2015TA26      Eur.Phys.J. A 51, 181 (2015)

P.Tamagno, C.De Saint Jean, O.Bouland, G.Noguere, P.Archier, E.Privas, O.Serot

From low- to high-energy nuclear data evaluations - Issues and perspectives on nuclear reaction models and covariances

doi: 10.1140/epja/i2015-15181-1
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2014AR04      Nucl.Data Sheets 118, 140 (2014)

P.Archier, G.Noguere, C.De Saint Jean, A.J.M.Plompen, C.Rouki

New JEFF-3.2 Sodium Neutron Induced Cross-sections Evaluation for Neutron Fast Reactors Applications: from 0 to 20 MeV

COMPILATION 23Na(n, x), E=0.4-20 MeV; calculated, evaluated σ including resonances using CONRAD code.

doi: 10.1016/j.nds.2014.04.020
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2014AR11      Nucl.Data Sheets 118, 488 (2014)

P.Archier, C.De Saint Jean, O.Litaize, G.Noguere, L.Berge, E.Privas, P.Tamagno

CONRAD Evaluation Code: Development Status and Perspectives

doi: 10.1016/j.nds.2014.04.114
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2014BA34      Nucl.Data Sheets 119, 186 (2014)

A.Bacquias, Ph.Dessagne, M.Kerveno, G.Rudolf, A.J.M.Plompen, J.C.Drohe, C.Rouki, N.Nankov, M.Nyman, C.Borcea, A.Negret, P.Archier, C.De Saint Jean, G.Noguere, C.Vaglio-Gaudard, A.Koning, A.Domula, K.Zuber, L.C.Leal

Neutron Inelastic Scattering Measurements for Na, Ge, Zr, Mo and U

NUCLEAR REACTIONS 238U(n, n'γ), (n, 2nγ), E=0-22 MeV; measured Eγ, Iγ; deduced γ transitions, σ; calculated σ using TALYS-1.2 and EMPIRE. Compared with other data. 92Mo(n, n'γ), 95Mo(n, n'γ), 96Mo(n, n'γ), 98Mo(n, n'γ), E=50-18000 keV; measured Eγ, Iγ; deduced γ transitions, yields. Measurements for some other targets sent for publications but not given here.

doi: 10.1016/j.nds.2014.08.052
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset22795.

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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2014DE16      Nucl.Data Sheets 118, 336 (2014)

C.De Saint Jean, E.Privas, P.Archier, G.Noguere

Estimation of Nuclear Reaction Model Parameter Covariances and the Related Neutron Induced Cross Sections with Physical Constraints

NUCLEAR REACTIONS 23Na(n, n'), E=1-3.5 MeV; calculated total σ; deduced optical model parameters, resonance parameters, covariances. 238U(n, x), E=25-750 keV; calculated total σ, covariances, resonance parameters. R-matrix and optical model.

doi: 10.1016/j.nds.2014.04.074
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2014LE12      Nucl.Data Sheets 118, 122 (2014)

L.C.Leal, G.Noguere, C.de Saint Jean, A.C.Kahler

239Pu Resonance Evaluation for Thermal Benchmark System Calculations

NUCLEAR REACTIONS 239Pu(n, F), (n, γ), (n, x), E=0.002-3 eV; calculated, evaluated σ; compared to data; deduced resonance parameters.

doi: 10.1016/j.nds.2014.04.016
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2014NO07      Nucl.Data Sheets 118, 349 (2014)

G.Noguere, P.Archier, C.De Saint Jean, B.Habert

On the Use of Zero Variance Penalty Conditions for the Generation of Covariance Matrix between Model Parameters

NUCLEAR REACTIONS 241Am(n, x), E=0.1-10 eV; calculated transmission and capture σ using Resonance Parameter Covariance Matrix; deduced resonance parameters. Compared with available data.

doi: 10.1016/j.nds.2014.04.077
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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
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2013LA34      Eur.Phys.J.Plus 127, 86 (2013)

C.Lampoudis, S.Kopecky, O.Bouland, F.Gunsing, G.Noguere, A.J.M.Plompen, C.Sage, P.Schillebeeckx, R.Wynants

Neutron transmission and capture cross section measurements for 241Am at the GELINA facility

NUCLEAR REACTIONS 241Am(n, γ), (n, X), E<110 eV; measured reaction products, Eγ, Iγ; deduced σ, yield, resonance parameters. Comparison with available data, JEFF and JENDL evaluated nuclear libraries.

doi: 10.1140/epjp/i2013-13086-0
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2012RO04      Nucl.Instrum.Methods Phys.Res. A672, 82 (2012)

C.Rouki, P.Archier, C.Borcea, C.De Saint Jean, J.C.Drohe, S.Kopecky, A.Moens, N.Nankov, A.Negret, G.Noguere, A.J.M.Plompen, M.Stanoiu

High resolution measurement of neutron inelastic scattering cross-sections for 23Na

NUCLEAR REACTIONS 23Na(n, n), (n, n'), 235U(n, F), E<4 MeV; measured reaction products, fission fragments, Eγ, Iγ. 23Na; deduced yields, σ, σ(θ), level energies and σ, J, π. Comparison with ENDF/B-VII, JEFF-3.1 evaluated nuclear libraries.

doi: 10.1016/j.nima.2012.01.004
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23137.

2011AR16      J.Korean Phys.Soc. 59, 915s (2011)

P.Archier, C.De Saint Jean, G.Noguere, J.Tommasi

23Na Evaluation with CONRAD for Fast Reactor Applications

COMPILATION 23Na(n, n'), E=2-20 MeV; evaluated σ using optical model CONRAD code, SVRE (Sodium Void Reactivity Effect) libraries, ZPPR experiments.

doi: 10.3938/jkps.59.915
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2011BO25      J.Korean Phys.Soc. 59, 833s (2011)

O.Bouland, G.M.Hale, J.E.Lynn, P.Talou, D.Bernard, O.Litaize, G.Noguere, C.De saint Jean, O.Serot

Towards Consistent Nuclear Models and Comprehensive Nuclear Data Evaluations

NUCLEAR REACTIONS 12C(n, X), E=0-6.5 MeV; analyzed σ using R matrix; deduced resonance widths. A=60-175(n, n'), E not given; calculated average prompt neutron multiplicity.

doi: 10.3938/jkps.59.833
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2011DE31      J.Korean Phys.Soc. 59, 1276s (2011)

C.De Saint Jean, B.Habert, P.Archier, G.Noguere, D.Bernard, J.Tommasi, P.Blaise

Uncertainty Evaluation of Nuclear Reaction Model Parameters using Integral and Microscopic Measurements with the CONRAD Code

doi: 10.3938/jkps.59.1276
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2011DE32      J.Korean Phys.Soc. 59, 1280s (2011)

C.De Saint Jean, B.Habert, G.Noguere, D.Bernard, J.M.Ruggieri, L.Leal, H.Derrien

Covariances for 239Pu Induced Cross Section in the Resonance Range using the CONRAD Code

COMPILATION 239Pu(n, X), E=0-1.000 eV; evaluated σ resonance parameters. 239Pu(n, F), (n, γ), E=0.05-30 eV; compiled, evaluated σ, resonances, Tl.

doi: 10.3938/jkps.59.1280
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2011LI53      J.Korean Phys.Soc. 59, 1900s (2011)

O.Litaize, C.De Saint Jean, G.Noguere, P.Archier

Statistical Analysis of a Set of Actinide Resolved Resonance Parameters with CONRAD Code

NUCLEAR STRUCTURE 238U; calculated, analyzed resonance parameters using CONRAD code; deduced different distributions. Compared with JEFF-3.1, ENDF-B/VII.0.

doi: 10.3938/jkps.59.1900
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2011NO13      Nucl.Phys. A870-871, 131 (2011)

G.Noguere, O.Litaize, P.Archier, C.De Saint Jean, P.Mutti

Average radiation widths of levels in natural xenon isotopes

NUCLEAR REACTIONS 124,126,128,129,130,131,132,134,136Xe(n, γ), (n, n'), E=3-4000 eV; calculated, re-analyzed neutron resonance data using R-matrix, deduced resonance parameters, level density, radiation width. Shape-analysis code REFIT, data codes CONRAD, SAMMY.

doi: 10.1016/j.nuclphysa.2011.09.004
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23211.

2011NO14      J.Korean Phys.Soc. 59, 1343s (2011)

G.Noguere, P.Archier, B.Habert, C.De Saint Jean, D.Bernard, J.Tommasi

Fission Product Cross Section Evaluations using Integral Experiments

NUCLEAR REACTIONS 155Gd(n, γ), E=0.01-200 eV; recalculated, reanalyzed σ using resonance parameters, sensitivity of burn-up to Gd capture; deduced 1st resonance parameters. 151Sm(n, γ), (n, X), E=1 keV-10 MeV; calculated σ. CONRAD code.

doi: 10.3938/jkps.59.1343
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2010NO02      Phys.Rev. C 81, 044607 (2010)


Neutron average cross sections of 237Np

NUCLEAR REACTIONS 237Np(n, γ), E=0-102 eV; analyzed σ, resonance parameters, neutron and gamma widths, s-, p-, d-wave strength functions from the simultaneous analysis of time-of-flight data measured at the GELINA, ORELA, KURRI, and LANSCE facilities. 237Np(n, X), E=0.1- 100 keV; calculated total and capture σ using the ECIS, TALYS, and CONRAD codes.

doi: 10.1103/PhysRevC.81.044607
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2010SA15      Phys.Rev. C 81, 064604 (2010)

C.Sage, V.Semkova, O.Bouland, P.Dessagne, A.Fernandez, F.Gunsing, C.Nastren, G.Noguere, H.Ottmar, A.J.M.Plompen, P.Romain, G.Rudolf, J.Somers, F.Wastin

High resolution measurements of the 241Am(n, 2n) reaction cross section

NUCLEAR REACTIONS 241Am(n, 2n), E=8-21 MeV; measured Eγ, Iγ; deduced σ, σ(E) by activation method. Comparison with nuclear model calculations using the TALYS code, and with evaluated data such as ENSDF/B-VII.

doi: 10.1103/PhysRevC.81.064604
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23114.

2010VA14      Nucl.Sci.Eng. 166, 267 (2010)

C.Vaglio-Gaudard, A.Santamarina, D.Bernard, G.Noguere, J.M.Ruggieri, J.F.Vidal, A.Lyoussi

New 56Fe Covariances for the JEFF3 File from the Feedback of Integral Benchmark Analysis

NUCLEAR REACTIONS 56Fe(n, n), (n, n'), (n, γ), E<20 MeV; calculated σ, uncertainties, covariance matrix. Comparison with BOLNA data.

doi: 10.13182/NSE09-103
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2009NO06      Ann.Nucl.Energy 36, 1059 (2009)

G.Noguere, P.Blaise, O.Litaize, D.Bernard, J.-M.Ruggieri

Group-average covariance matrices for the hafnium isotopes of interest for light water reactor applications

doi: 10.1016/j.anucene.2009.06.001
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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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset22956.

2009RI02      Nucl.Sci.Eng. 162, 178 (2009)

E.Rich, A.Tudora, G.Noguere, J.Tommasi, J.-F.Lebrat

Modeling of the n + 242Pu Reactions for Fast Reactor Applications

NUCLEAR REACTIONS 242Pu(n, X), E < 22 MeV; calculated fission cross sections. 242Pu(n, n), E=0.57-1.50 Mev; calculated σ(θ). 242Pu(n, n'), E=0.57 MeV; calculated σ(θ). 242Pu(n, xn), E < 22 MeV; calculated cross section. 242Pu(n, γ), E < 400 MeV; calculated σ.

doi: 10.13182/NSE162-178
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2008NO06      Ann.Nucl.Energy 35, 2259 (2008)

G.Noguere, J.-Ch.Sublet

A nuclear data oriented interface code for processing applications

doi: 10.1016/j.anucene.2008.09.001
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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
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2006LA09      Eur.Phys.J. A 27, 349 (2006)

P.Lautesse, L.Nalpas, R.Dayras, M.F.Rivet, M.Parlog, E.Bisquer, B.Borderie, R.Bougault, P.Buchet, J.L.Charvet, A.Chbihi, M.Colonna, A.Demeyer, P.Desesquelles, J.D.Frankland, E.Galichet, E.Gerlic, D.C.R.Guinet, R.Legrain, N.Le Neindre, O.Lopez, L.Manduci, A.M.Maskay, G.Noguere, E.Rosato, R.Roy, C.Schmitt, M.Stern, B.Tamain, E.Vient, M.Vigilante, C.Volant, J.P.Wieleczko, and the INDRA Collaboration

Evolution of the fusion cross-section for light systems at intermediate energies

NUCLEAR REACTIONS 58Ni(36Ar, X), E=32-95 MeV/nucleon; measured fragments transverse energy and charge distributions, proton and alpha invariant σ, fusion σ. 58Ni(58Ni, X), E=32-90 MeV/nucleon; measured fragments transverse energy and charge distributions, fusion σ. Comparison with dynamical reaction calculations, other reactions discussed.

doi: 10.1140/epja/i2005-10272-2
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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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset22948. Data from this article have been entered in the XUNDL database. For more information, click here.

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