Sfoglia per Rivista  ANNALS OF NUCLEAR ENERGY

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Analysis of ASTEC-Na capabilities for simulating a loss of flow CABRI experiment 1-gen-2016 Ederli, S.; Bandini, G.
Analysis of the temperature distribution in the pin bundle of the CIRCE facility 1-gen-2020 Buzzi, F.; Pucciarelli, A.; Galleni, F.; Tarantino, M.; Forgione, N.
Analysis of thermal stratification phenomena in the CIRCE-HERO facility 1-gen-2020 Buzzi, F.; Pucciarelli, A.; Galleni, F.; Tarantino, M.; Forgione, N.
Application of MCNP for predicting power excursion during LOCA in Atucha-2 PHWR 1-gen-2015 Parisi, C.
An approach to the experimental validation of the fission multiplying blanket of hybrid fusion fission systems 1-gen-2021 Salvatores, M.; Orsitto, F.; Carta, M.; Burgio, N.; Fabrizio, V.; Falconi, L.; Palomba, M.; Panza, F.
ASTEC code DBA analysis of a passive mitigation strategy on a generic IRIS SMR 1-gen-2021 Maccari, P.; Mascari, F.; Ederli, S.; Meloni, P.; Manservisi, S.
CFD thermo-hydraulic analysis of the CIRCE fuel bundle 1-gen-2017 Tarantino, M.; di Piazza, I.
Conceptual design of a sub-critical Pb-cooled Accelerator Driven System (ADS) fuelled by (Th-LEU) 1-gen-2017 Carta, M.
A correction and a clarification to "optimizing variance reduction in Monte Carlo eigenvalue calculations that employ the source iteration approach" 1-gen-2015 Burn, K. W.
Coupled simulations of the NACIE facility using RELAP5 and ANSYS FLUENT codes 1-gen-2017 Di Piazza, I.
Effects of cross sections library parameters on the OECD/NEA Oskarshamn-2 benchmark solution 1-gen-2015 Parisi, C.; Balestra, P.
Estimate of the reactivity of the VENUS-F subcritical configuration using a Monte Carlo MSM method 1-gen-2015 Fabrizio, V.; Carta, M.; Bianchini, G.
Generic Containment: Detailed comparison of containment simulations performed on plant scale 1-gen-2014 Sangiorgi, M.
Identification and categorisation of safety issues for ESNII reactor concepts. Part I: Common phenomena related to materials 1-gen-2016 Burgazzi, L.
Impact of a security event at a TRIGA reactor 1-gen-2015 Rocchi, F.
Inhibition of iron corrosion in high temperature stagnant liquid lead: A molecular dynamics study 1-gen-2013 Celino, M.
The Monte Carlo GPT methodology for the analysis of ratios of functionals bilinear with the real and adjoint neutron fluxes 1-gen-2017 Santagata, A.; Burgio, N.
The neutronic modelling of the VENUS-F critical core experiments with the ERANOS deterministic code (FREYA EU FP7 project) 1-gen-2018 Peluso, V.; Carta, M.; Fabrizio, V; Bianchini, G.; Sarotto, M.
Nuclear data target accuracy requirements for advanced reactors: The ALFRED case 1-gen-2021 Castelluccio, D. M.; Grasso, G.; Lodi, F.; Peluso, V. G.; Mengoni, A.
On the allowed sub-criticality level of lead (-bismuth) cooled ADS: the EU FP6 EFIT and FP7 FASTEF cases 1-gen-2017 Sarotto, M.
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