DocumentCode
2936146
Title
Degradation of plasma facing materials due to severe thermal shocks
Author
Rodig, M. ; Duwe, R. ; Linke, J. ; Qian, R.H. ; Schuster, A.
Author_Institution
EURATOM Assoc., Forschungszentrum Julich GmbH, Germany
Volume
2
fYear
1997
fDate
6-10 Oct 1997
Firstpage
865
Abstract
During off-normal plasma operation scenarios the high heat flux components in future thermonuclear devices such as ITER will be subjected to severe thermal shocks. Plasma disruptions with deposited energy densities of 100 MJm-2 and beyond are the most essential damaging mechanisms. However, a significant fraction of the incident energy will be absorbed by a dense cloud of ablation vapor, hence reducing the effective energy density at the plasma facing surface significantly. Beside material erosion, the formation of cracks in the recrystallized zone and in the underlying material will have strong impact on the integrity of the PFM. Also plasma instabilities on a much longer time scale, i.e. with a duration of 0.3 to 1.0 s have to be anticipated. These VDEs (vertical displacement events) result in deposited energy densities of approx. 60 MJm-2. In contrast to the rather short disruption events in addition to surface effects, also material damage to the bulk material and to the joining zone has to be considered
Keywords
fusion reactor materials; fusion reactor safety; thermal stress cracking; wear; 0.3 to 1 s; ITER; ablation vapor; cracks; damaging mechanisms; dense cloud; fusion reactors; high heat flux components; joining zone; material erosion; offnormal plasma operation scenarios; plasma disruptions; plasma facing materials degradation; plasma instabilities; reactor safety; recrystallized zone; severe thermal shocks; surface effects; thermonuclear devices; vertical displacement events; Conducting materials; Electric shock; Electron beams; Joining materials; Plasma density; Plasma devices; Plasma materials processing; Surface cracks; Thermal degradation; Thermal loading;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location
San Diego, CA
Print_ISBN
0-7803-4226-7
Type
conf
DOI
10.1109/FUSION.1997.687761
Filename
687761
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