2010
DOI: 10.1134/s1027451010040014
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Plasma-facing materials for fusion devices

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Cited by 21 publications
(14 citation statements)
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References 71 publications
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“…D into depth at 300 K is not different between a C material, which exhibits a graphite structure (pyrolytic graphite), and a C material, which exhibits an amorphous structure (a-C). Furthermore, the diffusion of D into depth is not affected by the W inclusions and thus by a changed trapping behaviour observed in a-C:W. By extrapolating the increase of the hydrogen inventory with fluence according to Φ X (with X = 0.1 at 300 -500 K) it can be shown that even after 0.5·10 5 400 s ITER-discharges in the T burning phase, which fits the scheduled operation time of the T burning phase of 20 years, the T inventory in a-C:W -built up by implantation and diffusion into depth -is at 300 -500 K two orders of magnitude below the safety limit of 700 g. This confirms that the build-up of the T inventory through the use of CFC is dominated at 300 -500 K by the co-deposition of T and C in remote areas, as already well known in literature [4,20,52].…”
Section: It Wassupporting
confidence: 70%
“…D into depth at 300 K is not different between a C material, which exhibits a graphite structure (pyrolytic graphite), and a C material, which exhibits an amorphous structure (a-C). Furthermore, the diffusion of D into depth is not affected by the W inclusions and thus by a changed trapping behaviour observed in a-C:W. By extrapolating the increase of the hydrogen inventory with fluence according to Φ X (with X = 0.1 at 300 -500 K) it can be shown that even after 0.5·10 5 400 s ITER-discharges in the T burning phase, which fits the scheduled operation time of the T burning phase of 20 years, the T inventory in a-C:W -built up by implantation and diffusion into depth -is at 300 -500 K two orders of magnitude below the safety limit of 700 g. This confirms that the build-up of the T inventory through the use of CFC is dominated at 300 -500 K by the co-deposition of T and C in remote areas, as already well known in literature [4,20,52].…”
Section: It Wassupporting
confidence: 70%
“…According to [1][2][3], tungsten is thought to be one of the most promising protective materials for the devices of thermonuclear reactors (TNR) that contact with plasma. An advantage of tungsten using is the negligible accumulation of hydrogen isotopes in this material.…”
Section: Introductionmentioning
confidence: 99%
“…The heating module is applied here to a Be/C/W materials wall, where the heating conductivity data is obtained from [26,27]. The wall thickness (distance of surface to the cool side) is L. The coolant temperature is fixed to T 0 = 400 K.…”
Section: The Temperature Distributionmentioning
confidence: 99%
“…where ρ and C p are the density (kg/m 3 ) and specific heat (J/(kg · K)) of the materials, respectively, and k(T ) = 1/(aT + b) is the heat conductivity (W/(m · K)), where the constants a and b are fitted from experiments [26]. The fitted form of k(T ) is used for convenience, as it allows an analytic solution at steady-state for simple cases, but is not an absolute requirement.…”
Section: Heating Modulementioning
confidence: 99%
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