NSR Query Results

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NSR database version of April 27, 2024.

Search: Author = J.Uhlir

Found 4 matches.

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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
Citations: PlumX Metrics

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
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31786.

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
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31771.

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
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31782.

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