DocumentCode
2541247
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
Volume
2
fYear
1995
fDate
30 Sep-5 Oct 1995
Firstpage
1031
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;
fLanguage
English
Publisher
ieee
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
Type
conf
DOI
10.1109/FUSION.1995.534401
Filename
534401
Link To Document