Vacuum vessel contact dose build-up from start to end of ITER operations

Author

Cambi, G. ; Cepraga, D.G. ; Frisoni, M. ; Carloni, F. ; Chiasera, A.

Author_Institution

Phys. Dept., Bologna Univ., Italy

fYear

2003

fDate

14-17 Oct. 2003

Firstpage

156

Lastpage

159

Abstract

The paper presents the ITER vacuum vessel (VV) contact dose build up evaluation from start to end of the machine life (expected to occur after about 20 years of operations, corresponding to an average neutron fluence of 0.5 MWa/m² on the first wall). The reference design used for ITER Generic Site Safety Report (GSSR) has been considered. Results are given for the inboard and outboard VV regions (and for both the front and rear 316L(N)-IG walls) in the radial equatorial plane. The Sn calculation sequence SCALENEA-1 (with the FISPACT-99 activation code) has been used for the analysis. The results point out that after only 20 seconds of irradiation at the nominal neutron power load, the contact dose of the most activated VV zone (i.e. the outboard region, front wall), reaches the hands-on limit of 10 μSv/h just after few months cooling time, requiring remote handling operations on that component in maintenance cells.

Keywords

Tokamak devices; fusion reactor design; fusion reactor materials; fusion reactor operation; fusion reactor safety; neutron effects; plasma toroidal confinement; 20 s; FISPACT-99 activation code; ITER Generic Site Safety Report; ITER operations; Sn calculation sequence SCALENEA-1; first wall; maintenance cells; neutron fluence; neutron irradiation; radial equatorial plane; remote handling operations; vacuum vessel contact dose build-up; Costs; Domestic safety; Neutrons; Physics; Plasma materials processing; Remote handling; Steel; Superconducting coils; Superconducting materials; Tin;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on

Print_ISBN

0-7803-7908-X

Type

conf

DOI

10.1109/FUSION.2003.1426611

Filename

1426611