NSR Query Results


Output year order : Descending
Format : Normal

NSR database version of April 27, 2024.

Search: Author = V.Juricek

Found 4 matches.

Back to query form



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
Citations: PlumX Metrics


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


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
Citations: PlumX Metrics

Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31825.


2014KO42      Nucl.Data Sheets 118, 561 (2014)

M.Kostal, J.Milcak, V.Rypar, V.Juricek, M.Svadlenkova, A.Kolros, B.Jansky

The Influence of Changes in Iron Cross Section in the Thermal Region between CENDL-3.1 and ENDF/B-VII.0

doi: 10.1016/j.nds.2014.04.135
Citations: PlumX Metrics


Back to query form