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Neutronic Analysis of FAST
By: Petrizzi, L.; Moro, F.; Esposito, B.; Marocco, D.; Pizzuto, A.; Cucchiaro, A.; Villari, R.; Brolatti, G.;
2010 / IEEE
Description
This item was taken from the IEEE Periodical ' Neutronic Analysis of FAST ' As part of the Fusion Advanced Studies Torus (FAST) project, a neutronic analysis has been performed, aimed to design optimization and radiological safety assessment. The neutron emissivity source foreseen for various FAST scenarios has been calculated and used as input for Monte Carlo calculations. The shielding analysis and nuclear heating calculations have been carried out with MCNP5 using a detailed 3-D model of the machine. The energy and spatial distributions of neutron fluxes have been used to perform activation analysis by means of the FISPACT code for safety assessment. The implications of the results on the design of the machine and on safety issues are presented and discussed.
Related Topics
Fusion Advanced Studies Torus Project
Optimization
Radiological Safety Assessment
Monte Carlo Calculations
Shielding Analysis
Nuclear Heating Calculations
Energy Distribution
Spatial Distribution
Neutron Fluxes
Fispact Code
Neutrons
Safety
Activation Analysis
Tokamaks
Plasma Density
Plasma Temperature
Performance Analysis
Design Optimization
Monte Carlo Methods
Heating
Neutronics
Activation
Fusion Advanced Studies Torus (fast)
Neutronic Analysis
Tokamak
Plasma Toroidal Confinement
Optimisation
Neutron Effects
Monte Carlo Methods
Tokamak Devices
Engineered Materials, Dielectrics And Plasmas
Engineering
Neutron Emissivity Source
