NSR Query Results

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NSR database version of April 27, 2024.

Search: Author = M.Marecek

Found 6 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

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
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31806.

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.

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.