NSR Query Results

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NSR database version of April 26, 2024.

Search: Author = M.Kostal

Found 22 matches.

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2024CZ02      Ann.Nucl.Energy 198, 110317 (2024)

T.Czakoj, M.Kostal, E.Novak, E.Losa, J.Simon, M.Schulc, F.Mravec, F.Cvachovec, J.Rataj, Z.Matej

Measurement of prompt neutron capture gamma coming from iron and chlorine

NUCLEAR REACTIONS Fe, Cl(n, γ), E ∼ 2.13 MeV; measured reaction products, Eγ, Iγ; deduced deduced γ-ray energies and relative photon flux, gamma leakage spectrum using ²⁵²Cf neutron source. Comparison with MCNP simulations, JENDl-5, ENDF/B-VIII.0 and JEFF-3.3 libraries data.

doi: 10.1016/j.anucene.2023.110317
Citations: PlumX Metrics

2024SC02      Nucl.Data Sheets 193, 1 (2024)

G.Schnabel, D.L.Aldama, T.Bohm, U.Fischer, S.Kunieda, A.Trkov, C.Konno, R.Capote, A.J.Koning, S.Breidokaite, T.Eade, M.Fabbri, D.Flammini, L.Isolan, I.Kodeli, M.Kostal, S.Kwon, D.Laghi, D.Leichtle, S.Nakayama, M.Ohta, L.W.Packer, Y.Qiu, S.Sato, M.Sawan, M.Schulc, G.Stankunas, M.Sumini, A.Valentine, R.Villari, A.Zohar

FENDL: A library for fusion research and applications

NUCLEAR REACTIONS ^1,2,3H, ^3,4He, ^6,7Li, ⁹Be, ^10,11B, ^12,13C, ^14,15N, ^16,17,18O, ¹⁹F, ^20,21,22Ne, ²³Na, ^24,25,26Mg, ²⁷Al, ^28,29,30Si, ³¹P, ^32,33,34S, ³⁶S, ^35,37Cl, ^36,38,40Ar, ^39,40,41K, ⁴⁰Ca, ^42,43,44Ca, ^46,48Ca, ⁴⁵Sc, ^{46,47,48,49,50}Ti, ^50,51V, ⁵⁰Cr, ^52,53,54Cr, ⁵⁵Mn, ⁵⁴Fe, ^56,57,58Fe, ⁵⁹Co, ⁵⁸Ni, ^60,61,62Ni, ⁶⁴Ni, ^63,65Cu, ⁶⁴Zn, ^66,67,68Zn, ⁷⁰Zn, ^69,71Ga, ⁷⁰Ge, ^72,73,74Ge, ⁷⁶Ge, ^79,81Br, ⁸⁹Y, ^{90,91,92,93,94}Zr, ⁹⁶Zr, ⁹³Nb, ⁹²Mo, ^{94,95,96,97,98}Mo, ¹⁰⁰Mo, ¹⁰³Rh, ^107,109Ag, ^106,108,110Cd, ^{111,112,113,114}Cd, ¹¹⁶Cd, ¹¹²Sn, ^{114,115,116,117,118,119,120}Sn, ^122,124Sn, ^121,123Sb, ¹²⁷I, ¹³³Cs, ^130,132,134Ba, ^{135,136,137,138}Ba, ^138,139La, ^{136,138,140,142}Ce, ¹⁴⁴Sm, ^{147,148,149,150}Sm, ¹⁵⁴Sm, ¹⁵²Gd, ^{154,155,156,157,158}Gd, ¹⁶⁰Gd, ^{162,164,166,168,170}Er, ¹⁶⁷Er, ^175,176Lu, ^{174,176,178,180}Hf, ^177,179Hf, ^180,181Ta, ^182,184,186W, ¹⁸³W, ^185,187Re, ^{190,192,194,196,198}Pt, ¹⁹⁵Pt, ¹⁹⁷Au, ^204,206,208Pb, ²⁰⁷Pb, ²⁰⁹Bi, ²³²Th, ^234,235U, ²³⁸U(n, X), ^1,2,3H, ³He, ^6,7Li, ⁹Be, ^10,11B, ^12,13C, ^14,15N, ^16,17,18O, ¹⁹F, ²³Na, ^24,25,26Mg, ²⁷Al, ^28,29,30Si, ³¹P, ^32,33,34S, ³⁶S, ^35,37Cl, ^36,38,40Ar, ^39,40,41K, ⁴⁰Ca, ^42,43,44Ca, ^46,48Ca, ⁴⁵Sc, ^{46,47,48,49,50}Ti, ^50,51V, ⁵⁰Cr, ^52,53,54Cr, ⁵⁵Mn, ⁵⁴Fe, ⁵⁸Fe, ⁵⁹Co, ⁵⁸Ni, ^60,61,62Ni, ⁶⁴Ni, ^63,65Cu, ⁶⁴Zn, ^66,67,68Zn, ⁷⁰Zn, ^69,71Ga, ⁷⁰Ge, ^72,73,74Ge, ⁷⁶Ge, ^79,81Br, ⁸⁹Y, ^{90,91,92,93,94}Zr, ⁹⁶Zr, ⁹³Nb, ⁹²Mo, ^{94,95,96,97,98}Mo, ¹⁰⁰Mo, ¹⁰³Rh, ^107,109Ag, ^106,108Cd, ^{110,111,112,113,114}Cd, ¹¹⁶Cd, ¹¹²Sn, ^{114,115,116,117,118,119,120}Sn, ^122,124Sn, ^121,123Sb, ¹²⁷I, ¹³³Cs, ^{130,132,134,136,138}Ba, ^135,137Ba, ^138,139La, ^{136,138,140,142}Ce, ^{152,153,154,155,156,157,158,159,160}Gd, ^155,157Gd, ^{162,164,166,168,170}Er, ¹⁶⁷Er, ^175,176Lu, ^{174,176,178,180}Hf, ^177,178,179Hf, ¹⁸¹Ta, ^{180,182,184,186}W, ¹⁸³W, ^185,187Re, ^{190,192,194,196,198}Pt, ¹⁹⁵Pt, ¹⁹⁷Au, ^204,206,208Pb, ²⁰⁷Pb, ²⁰⁹Bi, ²³²Th, ²³⁵U, ²³⁸U(p, X), E<3000 MeV; analyzed ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, INDEN-1.0, JENDL-4, JENDL/HE-2007, JEFF-3.1.1, FENDL-3.2 , TENDL-2010, TENDL-2011, TENDL-2014, TENDL-2015, TENDL-2019 libraries data; deduced recommended σ data coordinated by the International Atomic Energy Agency (IAEA) Nuclear Data Section (NDS).

doi: 10.1016/j.nds.2024.01.001
Citations: PlumX Metrics

2024ZM01      Appl.Radiat.Isot. 205, 111194 (2024)

M.Zmeskal, M.Kostal, J.Simon, D.Chvatil, P.Krist

Experimental validation of ²³Na(γ, n)²²Na cross section

NUCLEAR REACTIONS ¹⁹⁷Au, ⁶⁵Cu, ²³Na(γ, n), E<17 MeV; measured reaction products; deduced spectral everaged σ. Comparison with IAEA/PD-2019, ENDF/B-VIII.0, JENDL-5 libraries, TALYS calculations. Microtron MT25.

doi: 10.1016/j.apradiso.2024.111194
Citations: PlumX Metrics

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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2022SC08      Appl.Radiat.Isot. 188, 110378 (2022)

M.Schulc, M.Kostal, T.Czakoj, E.Novak, J.Simon, N.Hynkova, R.Capote

Spectrum averaged cross section measurements of lutetium using standard ²⁵²Cf neutron source

NUCLEAR REACTIONS ¹⁷⁵Lu(n, 2n), (n, 3n), (n, p), ¹⁷⁶Lu(n, n'), E ∼ 2 MeV; measured reaction products, Eγ, Iγ; deduced σ. Comparison with EXFOR, JEFF-3.3 and ENDF/B-VIII.0 libraries.

doi: 10.1016/j.apradiso.2022.110378
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31855.

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

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.

2020SC13      Appl.Radiat.Isot. 166, 109313 (2020)

M.Schulc, M.Kostal, J.Simon, F.Brijar, T.Czakoj, J.Pipster Maly

Constraining high energy tail of ²³⁵U(n_th, f) prompt fission neutron spectrum

NUCLEAR REACTIONS ²³⁵U(n, F), ¹⁹⁸Au(n, γ), E thermal; measured reaction products; deduced σ, reaction rates. Comparison with JEFF-3.3 and ENDF/B-VIII libraries ²³⁵U prompt neutron fission spectrum (PFNS).

doi: 10.1016/j.apradiso.2020.109313
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31828.

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.

2020TR01      Nucl.Data Sheets 163, 1 (2020)

A.Trkov, P.J.Griffin, S.P.Simakov, L.R.Greenwood, K.I.Zolotarev, R.Capote, D.L.Aldama, V.Chechev, C.Destouches, A.C.Kahler, C.Konno, M.Kostal, M.Majerle, E.Malambu, M.Ohta, V.G.Pronyaev, V.Radulovic, S.Sato, M.Schulc, E.Simeckova, I.Vavtar, J.Wagemans, M.White, H.Yashima

IRDFF-II: A New Neutron Metrology Library

doi: 10.1016/j.nds.2019.12.001
Citations: PlumX Metrics

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

2019SC01      Appl.Radiat.Isot. 143, 132 (2019)

M.Schulc, M.Kostal, R.Capote, E.Novak, J.Simon, N.Burianova, A.Wallner

Validation of selected (n, 2n) dosimetry reactions in IRDFF-1.05 library

NUCLEAR REACTIONS ⁵⁹Co, ¹⁹⁷Au, ¹⁶⁹Tm, ⁵⁵Mn, ⁹³Nb, ⁸⁹Y(n, 2n), ⁵⁹Co(n, p), E ∼ 2 MeV; measured reaction products, Eγ, Iγ; deduced spectrum-averaged σ. Comparison with IRDFF-1.05, ENDF/B-VII.1 libraries.

doi: 10.1016/j.apradiso.2018.10.027
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31789.

2019SC13      Appl.Radiat.Isot. 151, 187 (2019)

M.Schulc, M.Kostal, E.Novak, R.Kubin, J.Simon

Application of ²⁵²Cf neutron source for precise nuclear data experiments

RADIOACTIVITY ²⁵²Cf(SF); measured fission products, En, In; deduced fast neutron leakage spectra for various benchmark sets including spheres of different materials. Comparison with ENDF/B-VII.1 library.

doi: 10.1016/j.apradiso.2019.06.012
Citations: PlumX Metrics

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
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.

2018SC04      Appl.Radiat.Isot. 133, 45 (2018)

M.Schulc, M.Kostal, D.Harutyunyan, E.Novak

Disentangling the ¹⁶O cross section using light water and heavy water benchmark assemblies

NUCLEAR REACTIONS ¹⁶O(n, n), (n, n'), (n, α), E=1-10 MeV; measured reaction products, En, In; deduced light and heavy water leakage neutron flux density, neutron fluences for the light and heavy water spheres. Comparison with calculations using ENDF/B-VII.0, ENDF/B-VIII.b4 and JENDL-4 nuclear data libraries.

doi: 10.1016/j.apradiso.2017.12.014
Citations: PlumX Metrics

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

2017SC12      Appl.Radiat.Isot. 128, 86 (2017)

M.Schulc, M.Kostal, D.Harutyunyan, P.Baron, E.Novak

On ⁵⁴Fe neutron cross section importance in iron

NUCLEAR REACTIONS ⁵⁴Fe(n, p), (n, α), E<7 MeV; measured reaction products, Eγ, Iγ; deduced reaction rates. Comparison with ENDF/B-VII.1, JEFF-3.2, JENDL-4.0 evaluated nuclear data libraries.

doi: 10.1016/j.apradiso.2017.06.025
Citations: PlumX Metrics

2014JA15      Nucl.Data Sheets 118, 551 (2014)

B.Jansky, Z.Turzik, E.Novak, M.Kostal, J.Rejchrt, A.I.Blokhin

Iron Filtered Neutron Spectra: Measurement and Comparison with Calculations Using Different Libraries

doi: 10.1016/j.nds.2014.04.132
Citations: PlumX Metrics

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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