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2019-04-16 Tesi di laurea Magistrale A burnup meta-model for application in fuel performance codes : development and verification for MOX fuel in pressurized water reactors ALTIERI, STEFANO
2022-06-24 Tesi di Dottorato Advancements in modelling the thermal-mechanical behaviour of MOX-fuelled pins and application to liquid-metal fast reactor conditions MAGNI, ALESSIO
2016-04-27 Tesi di laurea Magistrale An innovative route for uranium carbide synthesis and densification using spark plasma sintering SALVATO, DANIELE
2022-04-28 Tesi di laurea Magistrale Analysis of an Am-bearing experimental fuel pin in a MYRRHA transient scenario Longoni, Luca
2021-04-28 Tesi di laurea Magistrale Application of the TRANSURANUS code to assess the MYRRHA fuel pin performance Delogu, Marco
2016-12-21 Tesi di laurea Magistrale Assessment of helium intra-granular behaviour in nuclear oxide fuels COGNINI, LUANA
2023-10-05 Tesi di laurea Magistrale Chromia-doped UO2 fuel: engineering modeling of chromium solubility and fission gas diffusivity NICODEMO, GIOVANNI
2016-04-27 Tesi di laurea Magistrale Development and assessment of computational fluid dynamics models for the study of natural circulation dynamics FANALE, FRANCESCO
2022-12-20 Tesi di laurea Magistrale Development of a data-driven surrogate model for helium production in fast reactor Am-bearing fuels KATSAMPIRIS, MARIOS-GEORGIOS
2022-04-28 Tesi di laurea Magistrale Development of MELCOR v2.2 input for the simulation of QUENCH-06 experiment Garbarini, Matteo
2020-07-07 Tesi di Dottorato Experimental Investigation and modelling of thermo-chemical and thermo-physical properties of fluorides for the molten salt fast reactor TOSOLIN, ALBERTO
2019-12-18 Tesi di laurea Magistrale Experimental investigation of Cs-Te-O and Cs-Mo-O fission product systems VOLFI, ANDREA
2016-04-27 Tesi di laurea Magistrale Experimental study of severe accident conditions in nuclear materials SOLDI, LUCA
2013-10-03 Tesi di laurea Magistrale Extension and application of a fuel pin performance code in the conceptual design of a lead cooled fast reactor PIZZOCRI, DAVIDE
2015-12-18 Tesi di laurea Magistrale Extension and validation of a transient fission gas release model for the TRANSURANUS fuel performance code BRUSCHI, ELISABARANI, TOMMASO
2023-07-18 Tesi di laurea Magistrale Fission gas release during design basis accidents : surrogate and physics-based models for conventional and meso-scale nuclear fuel codes PETROSILLO, GIACOMO
2012-04-23 Tesi di laurea Magistrale High temperature behaviour of nuclear materials investigated by laser heating and fast pyrometry QUAINI, ANDREACAPRIOTTI, LUCA
2013-07-23 Tesi di laurea Magistrale High temperature investigation of nanostructured actinide oxides CAPPIA, FABIOLA
2020-06-06 Tesi di laurea Magistrale Integral validation of an intra-granular fission gas behavior model with the BISON fuel performance code ROTA, GIUSEPPE
2021-06-03 Tesi di Dottorato Investigation of helium behaviour in oxide nuclear fuel COGNINI, LUANA
Mostrati risultati da 1 a 20 di 37
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