Tristan Calvet Yiqiang Wang Minh-Son Pham Catrin Davies
Sandwich-type cooling pipes of the first wall of future fusion nuclear reactors (i.e. DEMO) will likely consist of tungsten brazed to a Reduced Activation Ferritic Martensitic (RAFM) steel. Under a high heat flux (HHF) (1-5 MW/m2) the mismatch in thermal expansion between tungsten and steel results in significant thermal stresses in the brazing …
PublishedA. SABBAGH J.W. BERKERY Y.S. PARK J.H. AHN Y. JIANG J.D. RIQUEZES J. BUTT J. BIALEK J.G. BAK M.J. CHOI S.H. HAHN J. KIM J. KO W.H. KO J.W. LEE J.H. LEE K.D. LEE L. TERZOLO S.W. YOON R.E. BELL M.D. BOYER K. ERICKSON B. LEBLANC M. PODESTA Z.R.WANG J. YOO C. HAM A. KIRK L. KOGAN D. RYAN A. THORNTON J. HOLLOCOMBE F.M. LEVINTON M.GALLANTE
Disruption prediction and avoidance is critical for ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the disruption event characterization and forecasting (DECAF) research effort are shown. The DECAF paradigm is primarily physics-based and provides q…
PreprintJ. W. Berkery S. A. Sabbagh J. Bialek Y. Jiang C. Ham L. Kogan D. Ryan A. Thornton G. Xia D. Battaglia Z. Wang A. Piccione Y. Andreopoulos L. Guazzotto S. Gibson Y. Q. Liu
In preparation for high fusion plasma performance operation of the newly operating spherical tokamak MAST-U, the equilibrium and stability properties of plasmas in the MAST database, as well as projections for MAST-U, are explored. The disruption event characterization and forecasting (DECAF) code is utilized to map disruptions in MAST, particul…
PreprintBin Zhu Nathanael Leung Winfried Kockelmann Saurabh Kabra Andrew J. London Michael Gorley Mark J. Whiting Yiqiang Wang Tan Sui
Eurofer97 steel is a primary structural material for the plasma facing-components of future fusion reactors. Laser welding is a promising technique that can overcome the challenges of remote handling and maintenance. However, the interaction of the induced residual stress distribution with the heterogeneous microstructure may degrade the mechanical…
Preprint PublishedBin Zhu Yiqiang Wang Jiří Dluhoš Andy J. London Michael Gorley Mark J. Whiting Tan Sui
The plasma-facing components of future fusion reactors, where the Eurofer97 is the primary structural material, will be assembled by laser-welding techniques. The heterogeneous residual stress induced by welding can interact with the microstructure, resulting in a degradation of mechanical properties and a reduction in joint lifetime. Here, a Xe
Preprint PublishedV.D. Vijayananda M. Mokhtarishirazabad Y. Wang M. Gorley D.M. Knowles M. Mostafavi
Small punch testing was carried out on Copper-Chromium-Zirconium alloy subjected to two heat treatment conditions –both quenched and one subjected to subsequent aging. The variation in the load displacement characteristics associated with the testing was attributed to differences in plastic and damage properties evolved as a consequence of these …
Preprint PublishedMarkus Kuhbach Andrew J. London Jing Wang Daniel K. Schreiber FranciscaMendez-Martin Iman Ghamarian Huma Bilal Anna Ceguerra
Atom probe tomography and related methods probe the 3D architecture of a material. Which software tools microscopists use and how these tools are connected into work flows makes a substantial contribution to the accuracy and precision of a materials characterization experiment. Typically, the tools of a specific community adapt results and methods …
Preprint PublishedLi Li Yueqiang Liu Guoliang Xia Y. F. Wang Q. B. Luan W. D. Zhang F. C. Zhong
A recently updated version of the MARS-F code [Y. Q. Liu et al. Phys. Plasmas 7, 3681 (2000); L. Li et al. Phys. Plasmas 25, 082512 (2018); G. L. Xia et al. Nucl. Fusion 59, 126035 (2019)] is utilized to numerically investigate the plasma screening effect on the applied resonant magnetic perturbation (RMP) field, assuming various equilibrium flo…
Preprint PublishedJ. Lion F. Warmer H. Wang C.D. Beidler S.I. Muldrew R. C. Wolf
We present modifications of the systems code Process that allow for a description of a general class of stellarator power plants, based on a stellarator coil-set and the respective MHD plasma equilibrium. For this, we modify Process such that each stellarator confi…
Preprint PublishedDavid Andres Marta Serrano Rebeca Hernandez Yiqiang Wang Mark Richardson
The use of small specimen test techniques (SSTT) to determine mechanical properties of irradiated materials has been studied over the previous decades both in fission and fusion programs, but also to characterise and optimise new materials by nuclear and non-nuclear communities. Currently a number of activities are running that focus on the standar…
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