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G

G. Wright

Researcher at University of Wisconsin-Madison

Publications -  6
Citations -  277

G. Wright is an academic researcher from University of Wisconsin-Madison. The author has contributed to research in topics: Divertor & Ion. The author has an hindex of 6, co-authored 6 publications receiving 262 citations.

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Hydrogen and helium trapping in tungsten under simultaneous irradiations

TL;DR: In this article, the authors measured hydrogen and helium trapping in polycrystalline tungsten under simultaneous He + -H + and He + −D + irradiation by thermal desorption spectroscopy.
Journal ArticleDOI

Overview of the Alcator C-Mod Research Program

S. D. Scott, +89 more
- 01 Oct 2007 - 
TL;DR: In this article, a phase contrast imaging diagnostic has been used to study the structure of Alfv?n cascades and turbulent density fluctuations in plasmas with an internal transport barrier.
Journal ArticleDOI

Influence of boronization on operation with high-Z plasma facing components in Alcator C-Mod

TL;DR: In this paper, the results of operation of Alcator C-Mod with all high-Z molybdenum plasma facing component (PFC) surfaces were reported, showing that without boron-coated PFCs energy confinement was poor (H ITER,89 ǫ √ 2.1%) due to high core moly bdenum (n Mo / n e  0.1%), and radiation.
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Dynamics of hydrogenic retention in molybdenum: First results from DIONISOS

TL;DR: The Dynamics of ION Implantation and Sputtering of Surfaces (DIONISOS) experiment is described in this paper, which features steady-state plasma exposure of material surfaces, with simultaneous, in situ, non-destructive depth profiling on the same surfaces with ion beam analysis (IBA).

An Assessment of the Current Data Affecting Tritium Retention and its Use to Project Towards T Retention in ITER

TL;DR: In this paper, the authors examined the assumptions underlying tritium retention in materials and, based on assessments of applicable data ranges for each parameter, made projections to ITER for two limiting cases of main chamber fluxes, low (10 23 /s) and high (10 24 /s), as well as for the standard ITER materials of Be first-wall, CFC strike points, W baffle and dome, and all other cases: all-C, all-W divertor and Be first wall.