NSR Query Results

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NSR database version of April 27, 2024.

Search: Author = L.Snoj

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2020RA11      Nucl.Data Sheets 167, 61 (2020)

V.Radulovic, R.Jacimovic, A.Pungercic, I.Vavtar, L.Snoj, A.Trkov

Characterization of the neutron spectra in three irradiation channels of the JSI TRIGA reactor using the GRUPINT spectrum adjustment code

doi: 10.1016/j.nds.2020.07.003
Citations: PlumX Metrics

2019SA56      Nucl.Instrum.Methods Phys.Res. B446, 19 (2019)

L.Salamon, B.Geslot, J.Heyse, S.Kopecky, P.Leconte, G.Noguere, C.Paradela, P.Schillebeeckx, L.Snoj

¹⁰⁷Ag and ¹⁰⁹Ag resonance parameters for neutron induced reactions below 1 keV

NUCLEAR REACTIONS ^107,109Ag(n, X), (n, γ), E<1 keV; measured reaction products, En, In, Eγ, Iγ; deduced neutron resonance parameters, resonance energy, neutron and radiation widths, resonance integrals, yields. Comparison with ENDF/B-VIII.0, JENDL-4.0 and JEFF-3.2 evaluated libraries.

doi: 10.1016/j.nimb.2019.03.012
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Data from this article have been entered in the EXFOR database. For more information, access X4 dataset23533.

2017MA37      Appl.Radiat.Isot. 127, 150 (2017)

R.Makwana, S.Mukherjee, L.Snoj, S.S.Barala, M.Mehta, P.Mishra, S.Tiwari, M.Abhangi, S.Khirwadkar, H.Naik

Spectrum average cross section measurement of ¹⁸³W (n, p)¹⁸³Ta and ¹⁸⁴W (n, p)¹⁸⁴Ta reaction cross section in ²⁵²Cf(sf) neutron field

NUCLEAR REACTIONS ^183,184W(n, p), E<16 MeV; measured reaction products using ²⁵²Cf spontaneous fission neutron source, Eγ, Iγ; deduced σ. The neutron spectra were calculated using Monte Carlo N Particle Code (MCNP). Comparison with EMPIRE 3.2.2 nuclear model code and experimental results.

doi: 10.1016/j.apradiso.2017.06.002
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset33107.

2015MA33      Appl.Radiat.Isot. 101, 101 (2015)

S.Manojlovic, A.Trkov, G.Zerovnik, L.Snoj

Capture cross section measurement analysis in the Californium-252 spectrum with the Monte Carlo method

NUCLEAR REACTIONS ¹⁹⁷Au, ²³²Th, ¹⁸¹Ta, ⁹⁸Mo, ⁶⁵Cu, ⁸⁴Sr(n, γ), E<2 MeV [from ²⁵²Cf(SF)]; calculated σ with the Monte Carlo method.

doi: 10.1016/j.apradiso.2015.03.023
Citations: PlumX Metrics
Data from this article have been entered in the EXFOR database. For more information, access X4 dataset31770.

2014RA01      Appl.Radiat.Isot. 84, 57 (2014)

V.Radulovic, Z.Stancar, L.Snoj, A.Trkov

Validation of absolute axial neutron flux distribution calculations with MCNP with ¹⁹⁷Au(n, γ)¹⁹⁸Au reaction rate distribution measurements at the JSI TRIGA Mark II reactor

NUCLEAR REACTIONS ¹⁹⁷Au(n, γ)¹⁹⁸Au, E thermal; calculated reaction rates. Comparison with experimental values, ENDF/B-VII.1 nuclear data library.

doi: 10.1016/j.apradiso.2013.11.027
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