DocumentCode :
3461579
Title :
First Wall Qualification Testing at SNL
Author :
Tanaka, T.J. ; Ying, Alice ; Narula, Manmeet ; Ulrickson, Michael A.
Author_Institution :
Sandia Nat. Lab., Albuquerque
fYear :
2007
fDate :
17-21 June 2007
Firstpage :
1
Lastpage :
4
Abstract :
The first wall of ITER will be a replaceable sandwich of beryllium tiles, water-cooled copper alloy, and a water-cooled stainless steel backing. The first wall will be subject to approximately 30,000 pulses of surface heating at levels of 0.2 - 0.5 MW/m2 and 5 - 10 W/cm3 of volumetric nuclear heating. At these low heating levels, the main failure mechanism is predicted to be fatigue, particularly at the interface between the copper alloy and beryllium tile. Six different party teams are proposing to produce the first wall for ITER To qualify the processes and materials for producing the first wall, small mock-ups will be subject to fatigue testing at Sandia National Laboratories´ (SNL) Plasma Materials Test Facility and at a European Union test facility. We propose that the failure of a joining process is determined by an increase of surface temperature over nominal temperatures for a given surface heat flux. If the joint between a Be tile and Cu alloy degrades, the path from the heated surface to the coolant in the copper alloy increases, which should result in a higher surface temperature. This paper will document the test setup and preliminary analysis of the fatigue testing and failure criteria at SNL.
Keywords :
Tokamak devices; copper alloys; failure (mechanical); fatigue testing; fusion reactor blankets; fusion reactor design; joining processes; plasma materials processing; stainless steel; ITER; Sandia National Laboratories; Tokamak; beryllium tiles; blanket module; failure mechanism; fatigue testing; first wall qualification testing; joining process; plasma materials; surface heat flux; surface heating; volumetric nuclear heating; water-cooled copper alloy; water-cooled stainless steel; Copper alloys; Failure analysis; Fatigue; Heating; Plasma temperature; Qualifications; Steel; Test facilities; Testing; Tiles; Blanket module; ITER; Tokamak; first wall shield;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
978-1-4244-1193-1
Electronic_ISBN :
978-1-4244-1194-8
Type :
conf
DOI :
10.1109/FUSION.2007.4337948
Filename :
4337948
Link To Document :
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