The Molten Salt Fast Reactor (MSFR) is a nuclear reactor concept under development in the framework of H2020-Euratom project SAMOSAFER. Given its peculiar characteristics as circulating-fuel reactor, new simulation tools need to be developed and tested for study. In this work, multiphysics solver previously OpenFOAM extended with functionalities analysis design. main focus modelling behavior Ga...

The naval industry has integrated the generation of energy through nuclear processes, due to large amount that is produced in these for example, ship NS OTTO HAHN, which used a propulsion plant with generated by reactor pressurized water (PWR), operated under fission process. Also, other examples are military ships and icebreakers. In order know contribution this type plants, work carries out m...

Model-independent reactor isotopic cross sections per fission are determined by global fits of the antineutrino data from High-Enriched Uranium (HEU) rates, Low-Enriched (LEU) and fuel evolution data. Taking account implicit quasi-linear relationship between fractions $^{239}\rm{Pu}$ $^{241}\rm{Pu}$ in LEU data, Inverse-Beta-Decay (IBD) yields their correlations fissionable isotopes $^{235}\rm{...

This summary deals with a fundamental question in any reactor model validation practice: given a body of available experiments, and an envisaged domain of reactor operating conditions (referred to as reactor application), can one develop a quantitative measure that measures the portion of the prior uncertainties of the reactor application that is covered by the available experiments? Coverage h...

The only significant development of the AUS system has been an extension.of the available cross-sections. That portion of the ENDF/B V data files which is unrestricted has been acquired from the IAEA Nuclear Data Section and the data processed for the AUS.ENDF2006 group library as required. In particular, a large set of fission product data has been processtid, sufficient for calculations of bo...

At present work, under initial inventory with Th and U, the evolution of nuclides in subcritical devices under given thermal, fast, hardening fast and fission neutron field are studied without the detail structure of sub-critical device and the burn-up being considered. It is supposed that the subcritical reactor consists of uniform in which the flux of neutron is homogeneous. The fissile nucli...