Search Results - "Žerovnik, G."

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    Computational analysis of the dose rates at JSI TRIGA reactor irradiation facilities by Ambrožič, K., Žerovnik, G., Snoj, L.

    Published in Applied radiation and isotopes (01-12-2017)
    “…The JSI TRIGA Mark II, IJS research reactor is equipped with numerous irradiation positions, where samples can be irradiated by neutrons and γ-rays…”
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    Nuclear data uncertainty propagation to integral responses using SANDY by Fiorito, L., Žerovnik, G., Stankovskiy, A., Van den Eynde, G., Labeau, P.E.

    Published in Annals of nuclear energy (01-03-2017)
    “…•SANDY is a code for the uncertainty propagation of nuclear data.•Nuclear data uncertainties/covariances are propagated via stochastic sampling.•Random samples…”
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    Experimental assessment of the kinetic parameters of the JSI TRIGA reactor by Filliatre, P., Jammes, C., Barbot, L., Fourmentel, D., Geslot, B., Lengar, I., Jazbec, A., Snoj, L., Z̆erovnik, G.

    Published in Annals of nuclear energy (01-09-2015)
    “…•Experimental data collected at the TRIGA reactor of the Jozef Stefan Institute.•Kinetic parameter measurements with cross spectral densities of fission…”
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    On the self-shielding factors in neutron activation analysis by Trkov, A., Žerovnik, G., Snoj, L., Ravnik, M.

    “…Whenever the sample size in neutron activation analysis cannot be made small enough, self-shielding effects need to be taken into account. When several…”
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    Analysis of neutron flux distribution for the validation of computational methods for the optimization of research reactor utilization by Snoj, L., Trkov, A, Jaćimović, R., Rogan, P., Žerovnik, G., Ravnik, M.

    Published in Applied radiation and isotopes (2011)
    “…In order to verify and validate the computational methods for neutron flux calculation in TRIGA research reactor calculations, a series of experiments has been…”
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    On the use of criticality and depletion benchmarks for verification of nuclear data by Fiorito, L., Romojaro, P., Cabellos, O., García-Hormigos, M., Hernandez-Solis, A., Sánchez-Fernández, S., Stankovskiy, A., Van den Eynde, G., Žerovnik, G.

    Published in Annals of nuclear energy (01-10-2021)
    “…•A nuclear data sensitivity method based on the random sampling is proposed.•Sensitivity plots are reported for the actinide concentrations in irradiated…”
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    An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation by Schillebeeckx, Peter, Verwerft, M., Romojaro, P., Žerovnik, G., Messaoudi, N., Alaerts, G., Fiorito, L., Govers, K., Paepen, J., Parthoens, Y., Pedersen, B., Stankovskiy, A., Van den Eynde, G., Wynants, R.

    Published in Frontiers in energy research (24-04-2023)
    “…A method to determine the neutron production rate of a spent nuclear fuel segment sample by means of non-destructive assay conducted under standard…”
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    Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations by Romojaro, P., Álvarez-Velarde, F., Kodeli, I., Stankovskiy, A., Díez, C.J., Cabellos, O., García-Herranz, N., Heyse, J., Schillebeeckx, P., Van den Eynde, G., Žerovnik, G.

    Published in Annals of nuclear energy (01-03-2017)
    “…•A nuclear data S/U analysis of the latest MYRRHA designs is presented in this work.•The calculations have been performed with different codes and…”
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    Validation of calculated self-shielding factors for Rh foils by Jaćimović, R., Trkov, A., Žerovnik, G., Snoj, L., Schillebeeckx, P.

    “…Rhodium foils of about 5 mm diameter were obtained from IRMM. One foil had thickness of 0.006 mm and three were 0.112 mm thick. They were irradiated in the…”
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    Random Sampling of Correlated Parameters – a Consistent Solution for Unfavourable Conditions by Žerovnik, G., Trkov, A., Kodeli, I.A., Capote, R., Smith, D.L.

    Published in Nuclear data sheets (01-01-2015)
    “…Two methods for random sampling according to a multivariate lognormal distribution – the correlated sampling method and the method of transformation of…”
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    Evaluation of Tungsten Neutron Cross Sections in the Resolved Resonance Region by Pigni, M.T., Leal, L.C., Dunn, M.E., Guber, K.H., Trkov, A., Žerovnik, G., Emiliani, F., Kopecky, S., Lampoudis, C., Schillebeeckx, P., Siegler, P.

    Published in Nuclear data sheets (01-04-2014)
    “…We generated a preliminary set of resonance parameters for 182,183,184,186W in the neutron energy range of thermal up to several keV. The evaluation…”
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    Molecular dynamics simulations of Mo nanoparticles sputtering under irradiation by Panetier, C, Ruiz-Moreno, A, Rossi, F, Roubille, T, Zerovnik, G, Plompen, A, Moncoffre, N, Pipon, Y

    Published in Physica scripta (01-12-2022)
    “…Abstract 99 Mo is an essential isotope in nuclear medicine, but the nuclear reactors used for their production reaching their end of life, problems of supply…”
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    Determination of Hardness and Residual-Stress Variations in Hardened Surface Layers With Magnetic Barkhausen Noise by Zerovnik, P., Grum, J., Zerovnik, G.

    Published in IEEE transactions on magnetics (01-03-2010)
    “…We use magnetic Barkhausen noise to assess the microstructure, hardness, and residual stresses in hardened surface layers. We performed measurements on…”
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    Delayed Gamma Measurements in Different Nuclear Research Reactors Bringing Out the Importance of Their Contribution in Gamma Flux Calculations by Fourmentel, D., Radulovic, V., Barbot, L., Villard, J.-F, Zerovnik, G., Snoj, L., Tarchalski, M., Pytel, K., Malouch, F.

    Published in IEEE transactions on nuclear science (01-12-2016)
    “…Neutron and gamma levels are key parameters in nuclear research reactors. In Material Testing Reactors, such as the future Jules Horowitz Reactor, under…”
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    Review of the natC(n,γ) cross section and criticality calculations of the graphite moderated reactor BR1 by Díez, C.J., Stankovskiy, A., Malambu, E., Žerovnik, G., Schillebeeckx, P., Van den Eynde, G., Heyse, J., Cabellos, O.

    Published in Annals of nuclear energy (01-10-2013)
    “…•Review of the experimental and evaluated data for natC(n,γ) and 12C(n,γ).•Comparison of ENDF/B-VII.1 and JEFF-3.1.2 within BR1 criticality calculations.•The…”
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