Nuclear shielding design study for JT-60 Super Upgrade

Author

Miya, N. ; Kamada, Y. ; Nakajima, S. ; Ninomiya, H. ; Oguri, S. ; Oikawa, A. ; Sakasai, A. ; Toyoshima, N. ; Nakagawa, S. ; Nakashima, K. ; Otsuka, M.

Author_Institution

Naka Fusion Establ., JAERI, Ibaraki, Japan

Volume

1

fYear

1993

fDate

11-15 Oct 1993

Firstpage

321

Abstract

The nuclear shielding design for the vacuum vessel of the JT-60SU has been studied for deuterium operation. A low activation material, Ti-6Al-4V, is proposed through a design study. A 25-40 cm thick water tank-type vacuum vessel using Ti-6Al-4V and boron (1% of ¹⁰B) doped water are shown to be the best choice. This design concept gave results consistent with the design requirements: the one-turn resistivity of the vacuum vessel is ~50 μΩ, and the dose inside the vessel is ~15 mrem/h a year after the shutdown. The total nuclear heating of the whole TF coil can be reduced to ~11 kW for a D-D fusion neutron rate of 1×10¹⁸/s

Keywords

aluminium alloys; boron; dosimetry; fusion reactor design; fusion reactor materials; fusion reactor safety; shielding; titanium alloys; vanadium alloys; water; 50 muohm; H₂O-B; JT-60 Super Upgrade; JT-60SU; Ti-6Al-4V; Ti-Al-V; dose; nuclear shielding design; one-turn resistivity; toroidal field coil heating; vacuum vessel; Biological materials; Heating; Humans; Neutrons; Plasma devices; Plasma materials processing; Steady-state; Superconducting coils; Superconducting magnets; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on

Conference_Location

Hyannis, MA

Print_ISBN

0-7803-1412-3

Type

conf

DOI

10.1109/FUSION.1993.518340

Filename

518340