DocumentCode
3128015
Title
High vacuum cryocondensation pumping of the ITER cryostat
Author
Wykes, M. ; Mack, A. ; Day, C. ; Antipenkov, A. ; Murdoch, D. ; Marrs, R.
Author_Institution
ITER JWS, Garching, Germany
fYear
2003
fDate
14-17 Oct. 2003
Firstpage
135
Lastpage
139
Abstract
Prior to cool-down of the ITER magnet system, the enveloping cryostat has to be evacuated to a low enough pressure to reduce gas convection and conduction heat loads to the magnet structures to an acceptable level (∼-0.1 mPa). In order to standardize cryopump designs to the greatest extent practical, the design of the cryostat high vacuum (HV) cryopump used for this evacuation is almost identical to that of the cryosorption pumps used for the torus primary pumping system, but without the cryosorbent (cryocondensation pumping). Additionally, the pump location has been moved from that described in the 2001 Final Design Report (under the cryostat lid) and is now at the lower port level, closer to the cryo-supply manifolds, thereby facilitating rationalization of the cryodistribution system. On account of the large area of warm vacuum-facing surfaces within the cryostat, including epoxy, the cryocondensation pumpdown is dominated by outgassing (helium within the cryostat vacuum envelope, resulting from small leaks in the liquid helium magnet coolant piping, is pumped by separate cryosorption refrigerator pumps). The pumpdown performance is assessed from a closed solution of the time-dependent gas balance, wherein the transient pressure is given by a power series of the elapsed time, the coefficients being functions of the effective pumping speed, 1 hour outgassing rate, and logarithmic decay index. It is shown that the series solution is convergent in the time domain of practical interest. We present the evolution of the cryostat pressure for various outgassing characteristics and demonstrate that the pumping provision is adequate, even under adverse outgassing scenarios.
Keywords
Tokamak devices; convection; cryopumping; cryostats; fusion reactor design; fusion reactor materials; heat conduction; outgassing; plasma toroidal confinement; superconducting magnets; ITER cryostat; ITER magnet system; conduction heat loads; cryodistribution system rationalization; cryopump designs; cryosorbent; cryosorption refrigerator pumps; cryostat vacuum envelope; cryosupply manifolds; effective pumping speed; elapsed time power series; epoxy; gas convection; high vacuum cryocondensation pumping; liquid helium magnet coolant piping; logarithmic decay index; lower port level; magnet structures; outgassing; time-dependent gas balance; torus primary pumping system; transient pressure; warm vacuum-facing surfaces; Coolants; Cryogenics; Heat pumps; Helium; Infrared heating; Magnetic separation; Optical arrays; Superconducting magnets; Vacuum systems; Valves;
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.2003.1426606
Filename
1426606
Link To Document