Tritium retention and removal on TFTR

Author

Mueller, D. ; Blanchard, AW ; Doyle, B.L. ; Hosea, J.C. ; Nagy, A. ; Pearson, G. ; Skinner, C.H. ; Ulrickson, M.A. ; Wampler, W.R. ; Zweben, S.J.

Author_Institution

Plasma Phys. Lab., Princeton Univ., NJ, USA

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

279

Abstract

Tritium retention and removal are critical issues for the success of ITER or any DT fusion reactor. The Tokamak Fusion Test Reactor, TFTR, is the first fusion facility to afford the opportunity to study the tritium retention and removal over an extended period. In TFTR, tritium accumulates on all surfaces with line of sight to the plasma by codeposition of tritium with carbon. Measurements of both deuterium and tritium retention fractions have yielded retention between 0.2 and 0.6 of the injected fuel in the torus. Tritium has been successfully removed from TFTR by glow discharge cleaning and by air purges. The in-vessel inventory was reduced by a factor of 2, facilitating machine maintenance. In TFTR, the amount of dust recovered from the TFTR vacuum vessel has varied from several grams to a few kilograms

Keywords

fusion reactor fuel; nuclear reactor maintenance; radiation decontamination; tritium; tritium handling; C; D; T; T removal; T retention; TFTR; Tokamak Fusion Test Reactor; air purges; fusion facility; glow discharge cleaning; injected fuel; invessel inventory; machine maintenance; vacuum vessel; Cleaning; Deuterium; Fuels; Fusion reactors; Glow discharges; Inductors; Plasma measurements; Surface discharges; Testing; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687037

Filename

687037