Title :
Preliminary critical heat flux assessment of the high efficiency thermal shield device
Author :
Pizzuto, A. ; Riccardi, B.
Author_Institution :
Assoc. EURATOM, ENEA, Rome, Italy
fDate :
30 Sep-5 Oct 1995
Abstract :
Fusion thermonuclear reactors require thermal shielding devices with the capability to withstand the energy coming from the plasma in the divertor region as safely as possible. To improve the performance and thus the margin achievable with the tubular or hypervapotron devices, a new innovative concept has been developed and successfully tested
Keywords :
fusion reactor design; fusion reactor safety; shielding; divertor region; fusion thermonuclear reactors; high efficiency thermal shield device; hypervapotron devices; preliminary critical heat flux assessment; tubular devices; Acceleration; Chromium; Circuit testing; Copper; Electron beams; Fluid flow; Fusion reactor design; Inductors; Plasma devices; Temperature;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534401
