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Titlebook: Diagnostics for Experimental Thermonuclear Fusion Reactors 2; Peter E. Stott,Giuseppe Gorini,Elio Sindoni Book 1998 Springer Science+Busin

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21#
發(fā)表于 2025-3-25 03:51:35 | 只看該作者
SPH Variants on Multi-GPU Architecturesbased on the Interim Design Report (IDR). Whereas the design of several major machine components (e.g. TF-coils) were changed considerably compared to the earlier Outline Design (OD), it was pointed out at the time that the overall objectives and the plasma performance remained in line with the requ
22#
發(fā)表于 2025-3-25 08:25:48 | 只看該作者
23#
發(fā)表于 2025-3-25 13:52:23 | 只看該作者
SPH Variants on Multi-GPU Architectures The results of an assessment of the overall performance of the System are presented and the areas where the probable performance falls below the target specifications are identified. The design and R&smp;D plans which are in place to address the shortcomings are outlined.
24#
發(fā)表于 2025-3-25 17:47:49 | 只看該作者
SPH Variants on Multi-GPU Architecturesdesign of relevant parts of the ITER machine, in particular the access points for diagnostics such as ports and blanket modules, has developed significantly.. Diagnostic equipment is still found in the three main port areas (equatorial, vertical and divertor) and in the blanket back plate, but no lo
25#
發(fā)表于 2025-3-25 23:21:34 | 只看該作者
https://doi.org/10.1007/978-3-030-71625-7r tokamaks. In the past years the design of most diagnostic systems inclusive of those for the divertor has progressed beyond the conceptual stage so that their expected performance can now be predicted using this design information and the results of 2D modelling of the divertor plasma in a regime
26#
發(fā)表于 2025-3-26 01:45:46 | 只看該作者
27#
發(fā)表于 2025-3-26 08:11:57 | 只看該作者
28#
發(fā)表于 2025-3-26 10:58:59 | 只看該作者
29#
發(fā)表于 2025-3-26 13:24:51 | 只看該作者
30#
發(fā)表于 2025-3-26 19:58:49 | 只看該作者
Zdzis?aw J. Krysiński,Janusz B. Zielińskie of the flux surface near the plasma boundary. Reflectometry can measure the location of a specified density layer near the separatrix and is expected to be especially useful in controlling the location of the plasma boundary during the long equilibrium phase of the discharge when magnetics signals
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