![]() These are then used for simple calculations of the fuel evolution and of the potential for the incineration of minor actinide waste. ![]() Neutron fluxes and spectra are calculated at several regions in the core: fuel cells, IPS cells and the two (Mo and Ac) isotope production cells. An asymptotic 232Th/233U mixture is considered, together with the standard MOX fuel and a possible 232Th/MOX starter. It also extends the application of the widely-used Geant4 program to the geometry of MYRRHA and to thorium. Thorium is often considered for ADS systems, and this is the first evaluation of the possibilities for thorium based fuels using a reactor design which has been developed in detail. /? or /H or /Help Opens this Help topic.Neutronics calculations have been performed of the MYRRHA ADS Reactor with a thorium-based fuel mixture, using the simulation programs MCNPX (Waters, 2002) and Geant4 (Agostinelli, 2003). ![]() The original project is restored when InventorView exits.
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