Neutronic analysis of FAST

Author

Villari, R. ; Cucchiaro, A. ; Esposito, B. ; Marocco, D. ; Moro, F. ; Petrizzi, L. ; Pizzuto, A. ; Brolatti, G.

Author_Institution

Assoc. EURATOM-ENEA sulla Fusione, Frascati, Italy

fYear

2009

fDate

1-5 June 2009

Firstpage

1

Lastpage

6

Abstract

As a part of the FAST (Fusion Advanced Studies Torus) 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; fusion reactor design; fusion reactor divertors; fusion reactor safety; neutron flux; nuclear engineering computing; radiology; shielding; FAST design; FISPACT code; Fusion Advanced Studies Torus; MCNP5; Monte Carlo calculations; activation analysis; divertor; neutron emissivity source; neutron fluxes; neutronic analysis; nuclear heating calculations; radiological safety assessment; shielding analysis; Activation analysis; Copper; Design optimization; Heating; Magnetic flux; Neutrons; Plasma density; Plasma temperature; Safety; Tokamaks; FAST; activation; neutronics;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on

Conference_Location

San Diego, CA

Print_ISBN

978-1-4244-2635-5

Electronic_ISBN

978-1-4244-2636-2

Type

conf

DOI

10.1109/FUSION.2009.5226506

Filename

5226506