NSR Query Results
Output year order : Descending NSR database version of April 26, 2024. Search: Author = M.Schulc Found 23 matches. 2024CZ02 Ann.Nucl.Energy 198, 110317 (2024) T.Czakoj, M.Kostal, E.Novak, E.Losa, J.Simon, M.Schulc, F.Mravec, F.Cvachovec, J.Rataj, Z.Matej Measurement of prompt neutron capture gamma coming from iron and chlorine NUCLEAR REACTIONS Fe, Cl(n, γ), E ∼ 2.13 MeV; measured reaction products, Eγ, Iγ; deduced deduced γ-ray energies and relative photon flux, gamma leakage spectrum using 252Cf neutron source. Comparison with MCNP simulations, JENDl-5, ENDF/B-VIII.0 and JEFF-3.3 libraries data.
doi: 10.1016/j.anucene.2023.110317
2024SC02 Nucl.Data Sheets 193, 1 (2024) G.Schnabel, D.L.Aldama, T.Bohm, U.Fischer, S.Kunieda, A.Trkov, C.Konno, R.Capote, A.J.Koning, S.Breidokaite, T.Eade, M.Fabbri, D.Flammini, L.Isolan, I.Kodeli, M.Kostal, S.Kwon, D.Laghi, D.Leichtle, S.Nakayama, M.Ohta, L.W.Packer, Y.Qiu, S.Sato, M.Sawan, M.Schulc, G.Stankunas, M.Sumini, A.Valentine, R.Villari, A.Zohar FENDL: A library for fusion research and applications NUCLEAR REACTIONS 1,2,3H, 3,4He, 6,7Li, 9Be, 10,11B, 12,13C, 14,15N, 16,17,18O, 19F, 20,21,22Ne, 23Na, 24,25,26Mg, 27Al, 28,29,30Si, 31P, 32,33,34S, 36S, 35,37Cl, 36,38,40Ar, 39,40,41K, 40Ca, 42,43,44Ca, 46,48Ca, 45Sc, 46,47,48,49,50Ti, 50,51V, 50Cr, 52,53,54Cr, 55Mn, 54Fe, 56,57,58Fe, 59Co, 58Ni, 60,61,62Ni, 64Ni, 63,65Cu, 64Zn, 66,67,68Zn, 70Zn, 69,71Ga, 70Ge, 72,73,74Ge, 76Ge, 79,81Br, 89Y, 90,91,92,93,94Zr, 96Zr, 93Nb, 92Mo, 94,95,96,97,98Mo, 100Mo, 103Rh, 107,109Ag, 106,108,110Cd, 111,112,113,114Cd, 116Cd, 112Sn, 114,115,116,117,118,119,120Sn, 122,124Sn, 121,123Sb, 127I, 133Cs, 130,132,134Ba, 135,136,137,138Ba, 138,139La, 136,138,140,142Ce, 144Sm, 147,148,149,150Sm, 154Sm, 152Gd, 154,155,156,157,158Gd, 160Gd, 162,164,166,168,170Er, 167Er, 175,176Lu, 174,176,178,180Hf, 177,179Hf, 180,181Ta, 182,184,186W, 183W, 185,187Re, 190,192,194,196,198Pt, 195Pt, 197Au, 204,206,208Pb, 207Pb, 209Bi, 232Th, 234,235U, 238U(n, X), 1,2,3H, 3He, 6,7Li, 9Be, 10,11B, 12,13C, 14,15N, 16,17,18O, 19F, 23Na, 24,25,26Mg, 27Al, 28,29,30Si, 31P, 32,33,34S, 36S, 35,37Cl, 36,38,40Ar, 39,40,41K, 40Ca, 42,43,44Ca, 46,48Ca, 45Sc, 46,47,48,49,50Ti, 50,51V, 50Cr, 52,53,54Cr, 55Mn, 54Fe, 58Fe, 59Co, 58Ni, 60,61,62Ni, 64Ni, 63,65Cu, 64Zn, 66,67,68Zn, 70Zn, 69,71Ga, 70Ge, 72,73,74Ge, 76Ge, 79,81Br, 89Y, 90,91,92,93,94Zr, 96Zr, 93Nb, 92Mo, 94,95,96,97,98Mo, 100Mo, 103Rh, 107,109Ag, 106,108Cd, 110,111,112,113,114Cd, 116Cd, 112Sn, 114,115,116,117,118,119,120Sn, 122,124Sn, 121,123Sb, 127I, 133Cs, 130,132,134,136,138Ba, 135,137Ba, 138,139La, 136,138,140,142Ce, 152,153,154,155,156,157,158,159,160Gd, 155,157Gd, 162,164,166,168,170Er, 167Er, 175,176Lu, 174,176,178,180Hf, 177,178,179Hf, 181Ta, 180,182,184,186W, 183W, 185,187Re, 190,192,194,196,198Pt, 195Pt, 197Au, 204,206,208Pb, 207Pb, 209Bi, 232Th, 235U, 238U(p, X), E<3000 MeV; analyzed ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, INDEN-1.0, JENDL-4, JENDL/HE-2007, JEFF-3.1.1, FENDL-3.2 , TENDL-2010, TENDL-2011, TENDL-2014, TENDL-2015, TENDL-2019 libraries data; deduced recommended σ data coordinated by the International Atomic Energy Agency (IAEA) Nuclear Data Section (NDS).
doi: 10.1016/j.nds.2024.01.001
2023KO09 Ann.Nucl.Energy 191, 109904 (2023) M.Kostal, T.Czakoj, P.Alexa, J.Simon, M.Zmeskal, M.Schulc, A.Krechlerova, T.Peltan, F.Mravec, F.Cvachovec, V.Rypar, R.Uhlar, O.Harkut, Z.Matej Measurement of dosimetrical cross sections with 14.05 MeV neutrons from compact neutron generator NUCLEAR REACTIONS Ti(n, X)47Sc, 58Ni, 46,48Ti, 56Fe, 24Mg, 59Co(n, p), 93Nb, 89Y, 197Au, 90Zr, 59Co, 55Mn, 169Tm(n, 2n), 59Co(n, α), 58Ni(n, X)57Co, E=14.05 MeV; measured reaction products; deduced σ, a large set of reaction rates with the low-emission neutron generator. Comparison with IRDFF-II, ENDF/B-VIII.0, JEFF-3.3, JENDL-4, CENDL-3.2 libraries.
doi: 10.1016/j.anucene.2023.109904
2022SC08 Appl.Radiat.Isot. 188, 110378 (2022) M.Schulc, M.Kostal, T.Czakoj, E.Novak, J.Simon, N.Hynkova, R.Capote Spectrum averaged cross section measurements of lutetium using standard 252Cf neutron source NUCLEAR REACTIONS 175Lu(n, 2n), (n, 3n), (n, p), 176Lu(n, n'), E ∼ 2 MeV; measured reaction products, Eγ, Iγ; deduced σ. Comparison with EXFOR, JEFF-3.3 and ENDF/B-VIII.0 libraries.
doi: 10.1016/j.apradiso.2022.110378
2021KO04 Appl.Radiat.Isot. 169, 109566 (2021) M.Kostal, E.Losa, M.Schulc, T.Czakoj, T.Peltan, J.Simon, V.Juricek, V.Rypar, N.Thiollay, C.Destouches, V.Radulovic, A.Trkov, R.Capote Testing of various neutron filters in reference neutron field in LR-0 reactor for nuclear data validation and verification NUCLEAR REACTIONS 55Mn(n, γ), E thermal; measured reaction products, Eγ, Iγ; deduced reaction rates. MCNP6 calculations, comparison with IRDFF and ENDF/B-VIII.0 library.
doi: 10.1016/j.apradiso.2020.109566
2020KO10 Ann.Nucl.Energy 140, 107119 (2020) M.Kostal, M.Schulc, E.Losa, J.Simon, N.Burianova, E.Novak, M.Marecek, J.Uhlir, T.Czakoj, V.Rypar, V.Juricek, R.Capote, A.Trkov A reference neutron field for measurement of spectrum averaged cross sections NUCLEAR REACTIONS 75As, 90Zr, 23Na, 89Y, 55Mn, 127I, 19F, 197Au(n, 2n), 27Al(n, α), 24Mg, 48Ti(n, p), E<15 MeV; measured reaction products, Eγ, Iγ; deduced spectrum averaged σ. Comparison with ENDF/B-VIII.0 and IRDFF-1.05 libraries evaluations.
doi: 10.1016/j.anucene.2019.107119
2020SC01 Appl.Radiat.Isot. 155, 108937 (2020) M.Schulc, M.Kostal, J.Simon, E.Novak, M.Marecek, R.Kubin Validation of IRDFF-II library by means of 252Cf spectral averaged cross sections NUCLEAR REACTIONS 46,47,48Ti, 58,60Ni, 24Mg(n, p), 58Ni(n, 2n), 27Al, 63(n, α), E<2 MeV; measured reaction products; deduced spectrum-averaged cross sections (SACS) for 252Cf. Comparison with IRDFF-II library.
doi: 10.1016/j.apradiso.2019.108937
2020SC13 Appl.Radiat.Isot. 166, 109313 (2020) M.Schulc, M.Kostal, J.Simon, F.Brijar, T.Czakoj, J.Pipster Maly Constraining high energy tail of 235U(nth, f) prompt fission neutron spectrum NUCLEAR REACTIONS 235U(n, F), 198Au(n, γ), E thermal; measured reaction products; deduced σ, reaction rates. Comparison with JEFF-3.3 and ENDF/B-VIII libraries 235U prompt neutron fission spectrum (PFNS).
doi: 10.1016/j.apradiso.2020.109313
2020SC14 Appl.Radiat.Isot. 166, 109355 (2020) M.Schulc, M.Kostal, J.Simon, E.Novak, V.Juricek, M.Marecek Measurement of very high threshold reactions using 252Cf source NUCLEAR REACTIONS 58Ni(n, X)57Co, 169Tm(n, 3n)167Tm, 197Au(n, 3n)195Au, 209Bi(n, 3n)207Bi, 209Bi(n, 4n)206Bi, E ∼ 2 MeV; measured reaction products, Eγ, Iγ; deduced spectral averaged cross sections (SACS), reaction rates. Comparison with IRDFF-II, ENDF/B-VIII, TENDL-2019 libraries.
doi: 10.1016/j.apradiso.2020.109355
2020TR01 Nucl.Data Sheets 163, 1 (2020) A.Trkov, P.J.Griffin, S.P.Simakov, L.R.Greenwood, K.I.Zolotarev, R.Capote, D.L.Aldama, V.Chechev, C.Destouches, A.C.Kahler, C.Konno, M.Kostal, M.Majerle, E.Malambu, M.Ohta, V.G.Pronyaev, V.Radulovic, S.Sato, M.Schulc, E.Simeckova, I.Vavtar, J.Wagemans, M.White, H.Yashima IRDFF-II: A New Neutron Metrology Library
doi: 10.1016/j.nds.2019.12.001
2019BU25 Appl.Radiat.Isot. 154, 108855 (2019) N.Burianova, M.Kostal, T.Bily, E.Losa, J.Simon, M.Schulc, V.Rypar Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor NUCLEAR REACTIONS 89Y(n, 2n), 46,47,48Ti(n, p), 54Fe(n, p), 63Cu(n, α), 93Nb(n, 2n), 58Ni(n, X)57Co, E thermal; measured reaction products, Eγ, Iγ; deduced σ. Comparison with IRDFF library, available data.
doi: 10.1016/j.apradiso.2019.108855
2019SC01 Appl.Radiat.Isot. 143, 132 (2019) M.Schulc, M.Kostal, R.Capote, E.Novak, J.Simon, N.Burianova, A.Wallner Validation of selected (n, 2n) dosimetry reactions in IRDFF-1.05 library NUCLEAR REACTIONS 59Co, 197Au, 169Tm, 55Mn, 93Nb, 89Y(n, 2n), 59Co(n, p), E ∼ 2 MeV; measured reaction products, Eγ, Iγ; deduced spectrum-averaged σ. Comparison with IRDFF-1.05, ENDF/B-VII.1 libraries.
doi: 10.1016/j.apradiso.2018.10.027
2019SC13 Appl.Radiat.Isot. 151, 187 (2019) M.Schulc, M.Kostal, E.Novak, R.Kubin, J.Simon Application of 252Cf neutron source for precise nuclear data experiments RADIOACTIVITY 252Cf(SF); measured fission products, En, In; deduced fast neutron leakage spectra for various benchmark sets including spheres of different materials. Comparison with ENDF/B-VII.1 library.
doi: 10.1016/j.apradiso.2019.06.012
2018KO06 Appl.Radiat.Isot. 135, 83 (2018) M.Kostal, Z.Matej, E.Losa, O.Huml, M.Stefanik, F.Cvachovec, M.Schulc, B.Jansky, E.Novak, D.Harutyunyan, V.Rypar On similarity of various reactor spectra and 235U prompt fission neutron spectrum NUCLEAR REACTIONS 235U(n, F)1NN, E thermal; analyzed available data; calculated neutron spectra, σ(E).
doi: 10.1016/j.apradiso.2018.01.028
2018SC02 Appl.Radiat.Isot. 132, 29 (2018) M.Schulc, M.Kostal, S.Simakov, V.Rypar, D.Harutyunyan, J.Simon, N.Burianova, E.Novak, B.Jansky, M.Marecek, J.Uhlir Validation of differential cross sections by means of 252Cf spectral averaged cross sections NUCLEAR REACTIONS 23Na(n, 2n), 54Fe(n, p), (n, α), 51Cr, 27Al(n, p), 27Mg, 27Al(n, α), 19F(n, 2n), 90Zr, 89Y(n, 2n), E<20 MeV;measured reaction products, Eγ, Iγ; deduced σ. Comparison with ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.b4, CENDL-3.1, JENDL-3.3, JENDL-4, JEFF-3.2, TENDL-2013, ROSFOND-2010, and IRDFF-v1.05 evaluated nuclear data libraries.
doi: 10.1016/j.apradiso.2017.11.008
2018SC04 Appl.Radiat.Isot. 133, 45 (2018) M.Schulc, M.Kostal, D.Harutyunyan, E.Novak Disentangling the 16O cross section using light water and heavy water benchmark assemblies NUCLEAR REACTIONS 16O(n, n), (n, n'), (n, α), E=1-10 MeV; measured reaction products, En, In; deduced light and heavy water leakage neutron flux density, neutron fluences for the light and heavy water spheres. Comparison with calculations using ENDF/B-VII.0, ENDF/B-VIII.b4 and JENDL-4 nuclear data libraries.
doi: 10.1016/j.apradiso.2017.12.014
2017KO01 Ann.Nucl.Energy 100, 42 (2017) M.Kostal, V.Rypar, M.Schulc, E.Losa, P.Baron, M.Marecek, J.Uhlir Measurement of 75As(n, 2n) cross section in well-defined spectrum of LR-0 special core NUCLEAR REACTIONS 75As(n, 2n), E thermal; measured reaction products, Eγ, Iγ; deduced σ. Comparison with ENDF/B-VII.0, ENDF/B-VII.1 JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries.
doi: 10.1016/j.anucene.2016.10.012
2017KO27 Appl.Radiat.Isot. 128, 92 (2017) M.Kostal, M.Schulc, V.Rypar, E.Losa, N.Burianova, J.Simon, M.Marecek, J.Uhlir Validation of zirconium isotopes (n, g) and (n, 2n) cross sections in a comprehensive LR-0 reactor operative parameters set NUCLEAR REACTIONS 90Zr(n, 2n), 96Zr(n, γ), E thermal; measured reaction products, En, In, Eγ, Iγ; deduced σ. Comparison with MCNP calculations using ENDF/B-VII.0, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND- 2010, and CENDL-3.1 transport libraries combined with the dosimetry cross sections extracted from the IRDFF library.
doi: 10.1016/j.apradiso.2017.06.023
2017SC12 Appl.Radiat.Isot. 128, 86 (2017) M.Schulc, M.Kostal, D.Harutyunyan, P.Baron, E.Novak On 54Fe neutron cross section importance in iron NUCLEAR REACTIONS 54Fe(n, p), (n, α), E<7 MeV; measured reaction products, Eγ, Iγ; deduced reaction rates. Comparison with ENDF/B-VII.1, JEFF-3.2, JENDL-4.0 evaluated nuclear data libraries.
doi: 10.1016/j.apradiso.2017.06.025
2016SC22 Appl.Radiat.Isot. 118, 277 (2016) M.Schulc, P.Baron, E.Novak, B.Jansky, D.Harutyunyan Measurement of reaction rates for different neutron induced reactions in 27Al NUCLEAR REACTIONS 27Al(n, γ), (n, p), (n, α), E<3 MeV; measured reaction products, Eγ, Iγ; deduced reaction rates; Comparison with ENDF/B-VII.0, ENDF/B-VII.1, CENDL-3.1, JENDL-3.3, JENDL-4, JEFF-3.2, TENDL-2013, ROSFOND-2010, IRDFF evaluated nuclear libraries.
doi: 10.1016/j.apradiso.2016.10.001
2016TO14 Eur.Phys.J. A 52, 236 (2016) B.Tomasik, M.Schulc, I.Melo, R.Kopecna Observables of non-equilibrium phase transition
doi: 10.1140/epja/i2016-16236-5
2014SC29 Phys.Rev. C 90, 064910 (2014) Anisotropic flow of the fireball fed by hard partons
doi: 10.1103/PhysRevC.90.064910
2010SC23 Eur.Phys.J. A 45, 91 (2010) Rapidity correlations of protons from a fragmented fireball
doi: 10.1140/epja/i2010-10984-0
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