DocumentCode :
3199705
Title :
Twin-screw extruder development for the ITER pellet injection system
Author :
Meitner, S.J. ; Baylor, L.R. ; Combs, S.K. ; Fehling, D.T. ; McGill, J.M. ; Rasmussen, D.A. ; Leachman, J.W.
Author_Institution :
Fusion Energy Div., Oak Ridge Nat. Lab., Oak Ridge, TN, USA
fYear :
2009
fDate :
1-5 June 2009
Firstpage :
1
Lastpage :
4
Abstract :
The ITER pellet injection system is comprised of devices to form and accelerate pellets, and will be connected to inner wall guide tubes for fueling, and outer wall guide tubes for ELM pacing. An extruder will provide a stream of solid hydrogen isotopes to a secondary section, where pellets are cut and accelerated with a gas gun into the plasma. The ITER pellet injection system is required to provide a plasma fueling rate of 120 Pa-m3/s (900 mbar-L/s) and durations of up to 3000 s. The fueling pellets will be injected at a rate up to 10 Hz and pellets used to trigger ELMs will be injected at higher rates up to 20 Hz. A twin-screw extruder for the ITER pellet injection system is under development at the Oak Ridge National Laboratory. A one-fifth ITER scale prototype has been built and has demonstrated the production of a continuous solid deuterium extrusion. The 27 mm diameter, inter-meshed, counter-rotating extruder screws are rotated at a rate up to ~5 rpm. Deuterium gas is pre-cooled and liquefied and solidified in separate extruder barrels. The pre-cooler consists of a deuterium gas filled copper coil suspended in a separate stainless steel vessel containing liquid nitrogen. The liquefier is comprised of a copper barrel connected to a Cryomech AL330 cryocooler, which has a machined helical groove surrounded by a copper jacket, through which the pre-cooled deuterium condenses. The lower extruder barrel is connected to a Cryomech GB-37 cryocooler to solidify the deuterium (at ¿15 K) before it is forced through the extruder die. The die forms the extrusion to a 3 mm × 4 mm rectangular cross section. Design improvements have been made to improve the pre-cooler and liquefier heat exchangers, and to limit the loss of extrusion through gaps in the screws. This paper will describe the design improvements for the next iteration of the extruder prototype.
Keywords :
Tokamak devices; coils; cryogenics; fusion reactor design; fusion reactor fuel; heat exchangers; plasma boundary layers; plasma instability; stainless steel; Cryomech AL330 cryocooler; Cryomech GB-37 cryocooler; ELM; FeCrCJk; ITER pellet injection system; Oak Ridge National Laboratory; accelerate pellets; copper jacket; deuterium gas filled copper coil; gas gun; inner wall guide tubes; liquefier heat exchangers; liquid nitrogen; machined helical groove; outer wall guide tubes; plasma fueling; solid deuterium extrusion; solid hydrogen isotopes; stainless steel vessel; twin-screw extruder; Acceleration; Copper; Deuterium; Fasteners; Hydrogen; Isotopes; Laboratories; Plasma accelerators; Prototypes; Solids; ITER; pellet injection; twin-screw extruder;
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.2009.5226408
Filename :
5226408
Link To Document :
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