DocumentCode :
3198970
Title :
Integration of laser techniques in a remote handled compact system for tokamak in vessel tritium and dust inventory, control and removal
Author :
Hernandez, C. ; Roche, H. ; Pocheau, C. ; Naiim-Habib, M. ; Patterlini, J.-C. ; Sibois, R. ; Lapeyre, M. ; Semerok, A. ; Doceul, L. ; Grisolia, C.
Author_Institution :
Inst. de Rech. sur la Fusion par Confinement Magnetique, CEA-IRFM, St. Paul-lez-Durance, France
fYear :
2009
fDate :
1-5 June 2009
Firstpage :
1
Lastpage :
4
Abstract :
During Tokamak operation, plasma interacts with the Plasma Facing Components (PFCs). Therefore, exposed matter is eroded and re-deposited on the surface by forming instable layers. For safety and operational reasons and due to the fact that these layers are able to trap part of the hydrogenated species (particularly tritium) in vessel inventory or pollute diagnostics, flake and produce dusts, these layers have to be, characterized and removed. Several techniques are under development to solve these ITER open issues but one of the most promising is the laser technique. It allows to obtain a controlled cleaning process (without PFC damage) and an on-line chemical analysis of the removed layers thanks to Laser Induced Breakdown Spectroscopy (LIBS). In order to avoid in vessel contamination or simply to do sampling, a dust collection system has to be developed in accordance with Tokamak environment. Such a diagnostic/cleaning system must be embedded in a miniature tool placed on a Multi Purpose Deployer (MDP) in order to be used without Tokamak conditioning break. It can be operated at a pressure range from atmospheric to Ultra High Vacuum (10-6 Pa) and at a temperature of 120°C.
Keywords :
Tokamak devices; fusion reactor instrumentation; fusion reactor materials; fusion reactor operation; fusion reactor safety; laser beam effects; physical instrumentation control; plasma diagnostics; plasma interactions; radioactive waste disposal; tritium handling; waste recovery; ITER; diagnostic/cleaning system; dust inventory; hydrogenated species; laser induced breakdown spectroscopy; laser technique Integration; multi purpose deployer; on-line chemical analysis; plasma facing components; plasma interacts; pollute diagnostics; remote handled compact system; temperature 120 degC; tokamak; tokamak operation; tritium removal; ultra high vacuum; waste recovery; Chemical lasers; Cleaning; Control systems; Optical control; Plasma diagnostics; Pollution; Process control; Safety; Surface contamination; Tokamaks; LIBS; diagnostic; integration; laser treatments; tritium removal; waste recovery;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
978-1-4244-2635-5
Electronic_ISBN :
978-1-4244-2636-2
Type :
conf
DOI :
10.1109/FUSION.2009.5226378
Filename :
5226378
Link To Document :
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