M. D. Richardson M. Gorley Y. Wang G. Aiello G. Pintsuk E. Gaganidze M. Richou J. Henry R. Vila M. Rieth
A technology readiness assessment has been carried out on materials under development within the EUROfusion materials work package (WPMAT). This covers materials for structural, high heat flux and functional applications (breeder materials and coatings are not covered). The baseline materials have been assigned Material Technology Readiness Levels …
Preprint PublishedS.A. Sabbagh J.W. Berkery A. Kirk Y.S. Park J.H. Ahn J.M. Bialek Y. Jiang J.D. Riquezes J.G. Bak K. Erickson A.H. Glasser C. Ham J. Hollocombe J. Kim J. Ko W.H. Ko L. Kogan J.H. Lee A. Thornton S.W. Yoon Z.R. Wang
Disruption prediction and avoidance is critical in ITER and reactor-scale tokamaks to maintain steady plasma operation and to avoid damage to device components. The present status and results from the physics-based disruption event characterization and forecasting (DECAF) research effort are shown for multiple tokamak devices. Present analysis of K…
Preprint PublishedYiqiang Wang Omar Mohamed Keren Dunn Tan Sui Mutaz Bashir Peter Copper Adomas Lukenskas Guiyi Wu Michael Gorley
Precipitation hardened Copper-Chromium-Zirconium (CuCrZr) alloy is a prime candidate for divertor components in future European DEMOnstration fusion reactors. To develop the DEMO Design Criteria for In-vessel Components (DDC-IC), the failure criterion of CuCrZr needs to be investigated. Hence, the effects of stress triaxiality and loading…
Preprint PublishedV.D. Vijayanand M. Mokhtarishirazabad J. Peng Y. Wang M. Gorley D.M. Knowles M. Mostafavi
Determining tensile properties from small punch test is being pursued actively in the nuclear industry due to the limited volume of material such tests use compared with standard tests which can be critical when considering active or development samples. One of the crucial challenges in harnessing the full potential of this technique is formulat…
Preprint PublishedDylan Agius Abdullah Al Mamun Chris A Simpson Christopher Truman Yiqiang Wang Mahmoud Mostafavi David Knowles
Crystal plasticity finite element (CPFE) modelling is an effective tool from which detailed information on the meso-scale behaviour of crystalline metallic systems can be extracted and used, not only to enhance the understanding of material behaviour under different loading conditions, but also to improve the structural integrity assessment of e…
Preprint PublishedLei Tang Kun Yan Biao Cai Yiqiang Wang Bin Liu Saurabh Kabra Moataz M Attallah Yong Liu
Deformation mechanisms of high entropy alloys (HEAs) at cryogenic temperatures have attracted extensive research interest. We used in situ neutron diffraction to study the tensile behavior of a face-centered- cubic HEA at 77 and 15 K and compared its stacking fault energy (SFE) at ambient and cryogenic temperatures. The SFE dropped from 28 mJm −2…
PublishedGuoliang Xia Yueqiang Liu L. Li C. J. Ham Z . Wang Shuo Wang
Effects of parallel and poloidal flows, as well as the flow shear, on the resistive wall mode (RWM) instability have been numerically investigated in toroidally rotating plasmas, utilizing a recently updated version of the MARS-F code (Liu Y Q et al 2000 Phys. Plasmas 7 3681). A significant difference between these flow…
Preprint PublishedT. Long J.S. Allcock L. Nie R. M. Sharples M. Xu R. Ke S. Zhang S. A. Silburn J. Howard B. Yuan Y. Yu Z.H. Wang X.M. Song L. Liu
A Doppler coherence imaging spectroscopy diagnostic has been developed on the HL- 2A tokamak for scrape-off-layer impurity plasma flow measurements. Two- dimensional imaging of line-averaged C2+ flow in the high-field-side scrape off layer with time resolution up to 1 ms, has been achieved successfully by this system. The spatial angular resolut…
Preprint PublishedJ. Morris M. Y. Ye S. Mao
The Chinese Fusion Engineering Test Reactor (CFETR) bridges the gap between ITER and a demonstration fusion power plant (DEMO). The primary objectives of CFETR are: demonstrate tritium self-sufficiency, ~1GW fusion power, operate in steady-state and have a duty cycle of 0.3-0.5 [1]. CFETR is in the pre-conceptual design phase and is currently envis…
Preprint PublishedN. Zhang Y. Q. Liu P. Piovesan V. Igochine D. L. Yu S. Wang G. Q. Dong G. Z. Hao G. L. Xia W. J. Chen L. Liu J. Q. Li X. Bai
Resistive plasma response to the n = 1 (n is the toroidal mode number) RMP field is systematically investigated for a high-beta hybrid discharge on ASDEX Upgrade. Both linear and quasi-linear response are modelled using the MARS-F and MARS-Q codes, respectively. Linear response computations show a large internal kink response when the plasma centra…
Preprint Published