Paper 
Title 
Page 
WPAE010 
Neutron Flux and Activation Calculations for a High Current Deuteron Accelerator

1192 

 A. Coniglio, M.P. Pillon, S. Sandri
ENEA C.R. Frascati, Frascati (Roma)
 M. D'Arienzo
CNR/RFX, Padova



Neutron analysis of the first Neutral Beam (NB) for the International Thermonuclear Experimental Reactor (ITER) was performed to provide the basis for the study of the following main aspects: personnel safety during normal operation and maintenance, radiation shielding design, transportability of the NB components in the European countries. The first ITER NB is a medium energy light particle accelerator. In the scenario considered for the calculation the accelerated particles are negative deuterium ions with maximum energy of 1 MeV. The average beam current is 13.3 A. To assess neutron transport in the ITER NB structure a mathematical model of the components geometry was implemented into MCNP computer code (MCNP version 4c2. "Monte Carlo NParticle Transport Code System." RSICC Computer Code Collection. June 2001). The neutron source definition was outlined considering both DD and DT neutron production. FISPACT code (R.A. Forrest, FISPACT2003. EURATOM/UKAEA Fusion, December 2002) was used to assess neutron activation in the material of the system components. Radioactive inventory and contact dose rate were assessed considering the potential operative scenarios.

