Search Results - "Pizzocri, D."

SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes by Pizzocri, D., Barani, T., Luzzi, L.

“…Bridging lower length-scale calculations with the engineering-scale simulations of fuel performance codes requires the development of dedicated…”
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An investigation of FeCrAl cladding behavior under normal operating and loss of coolant conditions by Gamble, K.A., Barani, T., Pizzocri, D., Hales, J.D., Terrani, K.A., Pastore, G.

“…Iron-chromium-aluminum (FeCrAl) alloys are candidates to be used as nuclear fuel cladding for increased accident tolerance. An analysis of the response of…”
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Modeling high burnup structure in oxide fuels for application to fuel performance codes. part I: High burnup structure formation by Barani, T., Pizzocri, D., Cappia, F., Luzzi, L., Pastore, G., Van Uffelen, P.

“…We propose a model describing the HBS formation and the progressive intra-granular xenon depletion in UO2. The HBS formation is modeled employing the…”
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Modeling intra-granular fission gas bubble evolution and coarsening in uranium dioxide during in-pile transients by Barani, T., Pastore, G., Magni, A., Pizzocri, D., Van Uffelen, P., Luzzi, L.

“…The description of intra-granular fission gas behavior during irradiation is a fundamental part of models used for the calculation of fission gas release and…”
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Modelling of thermal conductivity and melting behaviour of minor actinide-MOX fuels and assessment against experimental and molecular dynamics data by Magni, A., Luzzi, L., Pizzocri, D., Schubert, A., Van Uffelen, P., Nevo, A. Del

“…•Modelling of thermal conductivity and melting temperature of minor actinide-MOX fuels.•Review of state-of-the-art data and correlations available in…”
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On the use of spectral algorithms for the prediction of short-lived volatile fission product release: Methodology for bounding numerical error by Zullo, G., Pizzocri, D., Luzzi, L.

“…Recent developments on spectral diffusion algorithms, i.e., algorithms which exploit the projection of the solution on the eigenfunctions of the Laplacian…”
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A surrogate model for the helium production rate in fast reactor MOX fuels by Pizzocri, D., Katsampiris, M.G., Luzzi, L., Magni, A., Zullo, G.

“…Helium production in the nuclear fuel matrix during irradiation plays a critical role in the design and performance of Gen-IV reactor fuel, as it represents a…”
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Modelling and assessment of thermal conductivity and melting behaviour of MOX fuel for fast reactor applications by Magni, A., Barani, T., Del Nevo, A., Pizzocri, D., Staicu, D., Van Uffelen, P., Luzzi, L.

“…•Derivation of original and comprehensive correlations for thermal conductivity and melting temperature of uranium-plutonium mixed oxide (MOX) nuclear…”
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Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions by Barani, T., Pastore, G., Pizzocri, D., Andersson, D.A., Matthews, C., Alfonsi, A., Gamble, K.A., Van Uffelen, P., Luzzi, L., Hales, J.D.

“…In this work, we present a model of fission gas behavior in U3Si2 under light water reactor (LWR) conditions for application in engineering fuel performance…”
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Application of the SCIANTIX fission gas behaviour module to the integral pin performance in sodium fast reactor irradiation conditions by Magni, A., Pizzocri, D., Luzzi, L., Lainet, M., Michel, B.

“…The sodium-cooled fast reactor is among the innovative nuclear technologies selected in the framework of the development of Generation IV concepts, allowing…”
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Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor by Magni, A., Barani, T., Belloni, F., Boer, B., Guizzardi, E., Pizzocri, D., Schubert, A., Van Uffelen, P., Luzzi, L.

“…•Extension of the TRANSURANUS fuel performance code to the MYRRHA pin cladding material.•Creep and void swelling modelling of DIN1.4970.•Application of…”
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Analysis of transient fission gas behaviour in oxide fuel using BISON and TRANSURANUS by Barani, T., Bruschi, E., Pizzocri, D., Pastore, G., Van Uffelen, P., Williamson, R.L., Luzzi, L.

“…The modelling of fission gas behaviour is a crucial aspect of nuclear fuel performance analysis in view of the related effects on the thermo-mechanical…”
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An effective numerical algorithm for intra-granular fission gas release during non-equilibrium trapping and resolution by Pastore, G., Pizzocri, D., Rabiti, C., Barani, T., Van Uffelen, P., Luzzi, L.

“…Fission gas release and gaseous swelling in nuclear fuel are driven by the transport of fission gas from within the fuel grains to grain boundaries…”
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On the intra-granular behaviour of a cocktail of inert gases in oxide nuclear fuel: Methodological recommendation for accelerated experimental investigation by Romano, M., Pizzocri, D., Luzzi, L.

“…Besides recent progresses in the physics-based modelling of fission gas and helium behaviour, the scarcity of experimental data concerning their combined…”
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Isotropic softening model for fuel cracking in BISON by Barani, T., Pizzocri, D., Pastore, G., Luzzi, L., Hales, J.D.

“…•Model to represent the effect of cracking as an isotropic softening of the material.•Computationally efficient means to account for fuel cracking in…”
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS by Zullo, G., Pizzocri, D., Magni, A., Van Uffelen, P., Schubert, A., Luzzi, L.

“…The behaviour of the fission gas plays an important role in the fuel rod performance. In a previous work, we presented a physics-based model describing intra-…”
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Physics-based modelling and validation of inter-granular helium behaviour in SCIANTIX by Giorgi, R., Cechet, A., Cognini, L., Magni, A., Pizzocri, D., Zullo, G., Schubert, A., Van Uffelen, P., Luzzi, L.

“…In this work, we propose a new mechanistic model for the treatment of helium behaviour at the grain boundaries in oxide nuclear fuel. The model provides a…”
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A reduced order model for fission gas diffusion in columnar grains by Pizzocri, D., Di Gennaro, M., Barani, T., Silva, F.A.B., Zullo, G., Lorenzi, S., Cammi, A.

“…In fast reactors, restructuring of the fuel micro-structure driven by high temperature and high temperature gradient can cause the formation of columnar…”
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A model describing intra-granular fission gas behaviour in oxide fuel for advanced engineering tools by Pizzocri, D., Pastore, G., Barani, T., Magni, A., Luzzi, L., Van Uffelen, P., Pitts, S.A., Alfonsi, A., Hales, J.D.

“…The description of intra-granular fission gas behaviour is a fundamental part of any model for the prediction of fission gas release and swelling in nuclear…”
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Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part I: SCIANTIX by Zullo, G., Pizzocri, D., Magni, A., Van Uffelen, P., Schubert, A., Luzzi, L.

“…When assessing the radiological consequences of postulated accident scenarios, it is of primary interest to determine the amount of radioactive fission gas…”
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