July 19-20, 2011 Hefei, ASIPP. Performance of W/Cu FGM in edge plasma of HT-7 tokamak. Zhu Dahuan Liu yang Chen Junling Institute of plasma physics, Chinese Academic of Science, China. Outline. Background and objectives Plasma exposure of W/Cu FGM and W-La 2 O 3 in HT-7 tokamak
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Performance of W/Cu FGM in edge plasma of HT-7 tokamak
Zhu Dahuan Liu yang Chen Junling
Institute of plasma physics, Chinese Academic of Science, China
- W/Cu FGM
◆ Engineer requirement
◆ Thermal mismatch
W or W-La2O3
- failure behavior
- failure mechanism
- Influence of La2O3 on thermal resistance
Schematic of device
W/Cu FGM block
（10 X 10 X 12mm）
◆ Main parameters:
Total shots ~210 cycles,
Average duration time ~1s.
Center cracks and exfoliation
propagation along interface
※ No failure was found at interface, but surface was damaged.
※ cracks originated from the edge and propagated to the inside and interface.
maximum surface temperature is 107oC → embrittlement behavior
maximum stress at the interface is 57 Mpa
(a) Temperature and (b) Stress distribution under 2MW/m2 (1s)
(a) 3D and (b) Surface distribution of von mises stress under typical transient flux 0.2 MJ/m2 (2ms)
maximum stress at the surface is 993 Mpa
(a)W-1%La2O3 composite; (b) pure W
Summary stress under typical transient flux 0.2 MJ/m
Future plan stress under typical transient flux 0.2 MJ/m
Thanks for your attention! stress under typical transient flux 0.2 MJ/m