Journal
THERMEC 2011, PTS 1-4
Volume 706-709, Issue -, Pages 835-+Publisher
TRANS TECH PUBLICATIONS LTD
DOI: 10.4028/www.scientific.net/MSF.706-709.835
Keywords
Tungsten; plasma facing components; nuclear fusion reactors; internal friction
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Tungsten is a promising armour material for plasma facing components of nuclear fusion reactors. Two materials with different density and purity have been examined by optical microscopy, X-ray diffraction (XRD), instrumented indentation tests (FIMEC) and mechanical spectroscopy. For both the materials yield stress and elastic modulus strictly depend on the residual porosity. Moreover, the material with higher porosity (approximate to 9%) is not stable and remarkable modulus variations are observed during heating. The IF spectrum exhibits a relaxation Q(-1) peak superimposed to an exponentially increasing background. The peak is a single Debye peak with activation energy H = 74.86 kJ mol(-1) and pre-exponential factor tau(0) = 1.76 x 10(-9) s that has been ascribed to dislocation interaction with intrinsic point defects (autointerstitial and substitutional).
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