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Proceedings Paper

Comparison between experimental and numerical determination of neutron-induced activation in low-activation materials
Author(s): Mario Pillon; M. Angelone; C. Arpesella; R. A. Forrest; J.-Ch. Sublet
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Paper Abstract

The need for studies of the activation of materials in the neutron fluxes encountered in D-T fusion devices has long been recognized as a key area of fusion technology programs. In this paper a comparison between experimental and numerical results of the induced radioactivity in a low activation material, the SiC/SiC fiber ceramic composite, is presented. The SiC/SiC fiber ceramic composite is a candidate material for the DEMO phase of a commercial fusion power station. This material was exposed to the neutron flux produced by a D-T neutron generator and the induced activity was carefully measured using the Low Background Counting Facility in the Gran Sasso laboratory. The neutron flux and spectra at the irradiation position have been determined using foil activation and numerical calculations with the Monte Carlo Code MCNP. These quantities have been used as input values for the activation code FISPACT and the cross section library EAF 4.1, to calculate the induced activity. The material composition and its impurities have been taken from existing data. The results of the comparison are discussed, focusing on the validation of the cross sections and the activity coming from the impurities.

Paper Details

Date Published: 27 February 1997
PDF: 4 pages
Proc. SPIE 2867, International Conference Neutrons in Research and Industry, (27 February 1997); doi: 10.1117/12.267858
Show Author Affiliations
Mario Pillon, ENEA (Italy)
M. Angelone, ENEA (Italy)
C. Arpesella, INFN (Italy)
R. A. Forrest, UKAEA (United Kingdom)
J.-Ch. Sublet, UKAEA (United Kingdom)

Published in SPIE Proceedings Vol. 2867:
International Conference Neutrons in Research and Industry
George Vourvopoulos, Editor(s)

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