DocumentCode
1401473
Title
Neutronic Analysis of FAST
Author
Villari, Rosaria ; Cucchiaro, Antonio ; Esposito, Basilio ; Marocco, Daniele ; Moro, Fabio ; Petrizzi, Luigino ; Pizzuto, Aldo ; Brolatti, Giorgio
Author_Institution
Fusion Technol. Unit, Associazione EURATOM-ENEA sulla Fusione, Frascati, Italy
Volume
38
Issue
3
fYear
2010
fDate
3/1/2010 12:00:00 AM
Firstpage
406
Lastpage
413
Abstract
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.
Keywords
Monte Carlo methods; Tokamak devices; neutron effects; optimisation; plasma toroidal confinement; FISPACT code; Fusion Advanced Studies Torus project; Monte Carlo calculations; energy distribution; neutron emissivity source; neutron fluxes; neutronic analysis; nuclear heating calculations; optimization; radiological safety assessment; shielding analysis; spatial distribution; tokamak; Activation; Fusion Advanced Studies Torus (FAST); neutronics;
fLanguage
English
Journal_Title
Plasma Science, IEEE Transactions on
Publisher
ieee
ISSN
0093-3813
Type
jour
DOI
10.1109/TPS.2009.2038915
Filename
5404428
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