NSR Query Results
Output year order : Descending NSR database version of May 6, 2024. Search: Author = M.Marecek Found 6 matches. 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
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
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
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
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