Neutronic analysis of FAST

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

Research output: Contribution to conferencePaper

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 alculations. 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. ©2009 IEEE.
Original languageEnglish
DOIs
Publication statusPublished - 2009
Externally publishedYes
Event2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009 - , United States
Duration: 1 Jan 2009 → …

Conference

Conference2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009
CountryUnited States
Period1/1/09 → …

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All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Nuclear and High Energy Physics

Cite this

Villari, R., Cucchiaro, A., Esposito, B., Marocco, D., Moro, F., Petrizzi, L., ... Brolatti, G. (2009). Neutronic analysis of FAST. Paper presented at 2009 23rd IEEE/NPSS Symposium on Fusion Engineering, SOFE 2009, United States. https://doi.org/10.1109/FUSION.2009.5226506