NSR Query Results

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NSR database version of April 27, 2024.

Search: Author = V.Rypar

Found 9 matches.

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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
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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
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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
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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
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31822.

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

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
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