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000844876 1001_ $$0P:(DE-HGF)0$$aSinclair, G.$$b0$$eCorresponding author
000844876 245__ $$aStructural evolution of tungsten surface exposed to sequential low-energy helium ion irradiation and transient heat loading
000844876 260__ $$aAmsterdam [u.a.]$$bElsevier$$c2017
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000844876 520__ $$aStructural damage due to high flux particle irradiation can result in significant changes to the thermal strength of the plasma facing component surface (PFC) during off-normal events in a tokamak. Low-energy He+ ion irradiation of tungsten (W), which is currently the leading candidate material for future PFCs, can result in the development of a fiber form nanostructure, known as “fuzz”. In the current study, mirror-finished W foils were exposed to 100 eV He+ ion irradiation at a fluence of 2.6 × 1024 ions m−2 and a temperature of 1200 K. Then, samples were exposed to two different types of pulsed heat loading meant to replicate type-I edge-localized mode (ELM) heating at varying energy densities and base temperatures. Millisecond (ms) laser exposure done at 1200 K revealed a reduction in fuzz density with increasing energy density due to the conglomeration and local melting of W fibers. At higher energy densities (∼ 1.5 MJ m−2), RT exposures resulted in surface cracking, while 1200 K exposures resulted in surface roughening, demonstrating the role of base temperature on the crack formation in W. Electron beam heating presented similar trends in surface morphology evolution; a higher penetration depth led to reduced melt motion and plasticity. In situ mass loss measurements obtained via a quartz crystal microbalance (QCM) found an exponential increase in particle emission for RT exposures, while the prevalence of melting from 1200 K exposures yielded no observable trend.
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000844876 7001_ $$0P:(DE-HGF)0$$aTripathi, J. K.$$b1
000844876 7001_ $$0P:(DE-HGF)0$$aDiwakar, P. K.$$b2
000844876 7001_ $$0P:(DE-Juel1)129747$$aLinke, J.$$b3$$ufzj
000844876 7001_ $$0P:(DE-HGF)0$$aHassanein, A.$$b4
000844876 7001_ $$0P:(DE-Juel1)129811$$aWirtz, Marius$$b5
000844876 773__ $$0PERI:(DE-600)2808888-8$$a10.1016/j.nme.2017.03.003$$gVol. 12, p. 405 - 411$$p405 - 411$$tNuclear materials and energy$$v12$$x2352-1791$$y2017
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