Results 41 to 50 of about 96,750 (196)

Impact of creep-fatigue interaction on divertor tungsten under high heat flux

Nuclear Materials and Energy, 2023
High heat flux as 20 MW m−2 during stationary operation can be foreseen in future fusion devices, leading to recrystallization and thermal creep in tungsten targets. Both recrystallization and thermal creep impact would play significant roles in service.
Yu-Zhong Jin, Hao Wang, Xiang Liu, You-Yun Lian, Fan Feng, Jian-bao Wang, Zong-jian Chai, Jiu-Peng Song, Xu-ru Duan   +8 more
doaj   +1 more source

Tungsten foil laminate for structural divertor applications – Analyses and characterisation of tungsten foil

Journal of Nuclear Materials, 2012
Abstract It has been attempted for several years to synthesise a tungsten material with a low brittle-to-ductile transition temperature and a high fracture toughness that can be used for structural parts. It was shown in our previous work that tungsten foil is ductile at room temperature and that this ductility can be transformed to bulk by ...
Reiser, J., Rieth, M., Dafferner, B., Hoffmann, A., Yi, X., Armstrong, D. E. J.   +5 more
openaire   +2 more sources

Improved erosion estimates for the STEP divertor

Nuclear Materials and Energy
Net tungsten erosion and deposition profiles are simulated for the outer and inner lower divertor of STEP, a spherical prototype fusion reactor targeting ∼ 2040.
A. Kirschner, S.S. Henderson, S. Brezinsek, J. Romazanov, C. Baumann, M. Kovari, Ch. Linsmeier   +6 more
doaj   +1 more source

The interplay of controlling the power exhaust and the tungsten content in ITER

Nuclear Materials and Energy, 2017
The main elements defining the tungsten content of an ITER plasma, i.e. the gross erosion, the prompt redeposition and the transport in the H-mode edge transport barrier are reviewed and it is investigated, whether the low tungsten concentration limit in
R. Dux, A. Loarte, C. Angioni, D. Coster, E. Fable, A. Kallenbach   +5 more
doaj   +1 more source

Heat Load Mitigation Studies in the W7‐X Stellarator Experiment

Contributions to Plasma Physics, EarlyView.
ABSTRACT During the experiments at the stellarator Wendelstein 7‐X (W7‐X) with fully water‐cooled plasma‐facing components (PFC), including carbon‐fiber composite (CFC) divertor targets with a thermal load capability of 10 MW/m2, high performance was achieved.
Dirk Naujoks, Amit Kharwandikar, Jasper Dettmar, Michael Endler, Joris Fellinger, Yu Gao, Joachim Geiger, Marcin Jakubowski, Thomas Sieber, Sebastian Thiede, Christian Voß, W7‐X Team   +11 more
wiley   +1 more source

Spectroscopic measurements of tungsten erosion in the ASDEX Upgrade divertor

Plasma Physics and Controlled Fusion, 1997
Tungsten erosion in the ASDEX Upgrade divertor has been measured by observing the WI emission at 400.9 nm. The sputtering yield is in the region of atoms/ion for typical divertor plasma conditions. By comparison of the measured sputtering yield with modelled sputtering yields one can conclude that tungsten erosion is dominated by plasma impurities ...
A Thoma, K Asmussen, R Dux, K Krieger, A Herrmann, B Napiontek, R Neu, J Steinbrink, M Weinlich, U Wenzel, the ASDEX Upgrade Team   +10 more
openaire   +3 more sources

Erosion, Screening, and Migration of Tungsten in the JET Divertor [PDF]

Nuclear Fusion, 2019
The erosion of tungsten (W), induced by the bombardment of plasma and impurity particles, determines the lifetime of plasma-facing components as well as impacting on plasma performance by the influx of W into the confined region. The screening of W by the divertor and the transport of W in the plasma determines largely the W content in the plasma core,
Brezinsek, S., Borodin, D., Huber, A., Baron-Wiechec, A., Borodkina, I., Coffey, I., Guillemaut, C., Heinola, K., Imrisek, M., Jachmich, S., Pawelec, E., Kirschner, A., Krat, S., Sergienko, G., Matthews, G., Mayer, M., Meigs, A., Wiesen, S., Widdowson, A.   +18 more
openaire   +8 more sources

First SOLPS‐ITER Simulation Study of Japanese DEMO on Leakage of Seeded Ar Impurity

Contributions to Plasma Physics, EarlyView.
ABSTRACT For JA DEMO, one of the grand challenges is efficiently handling the extreme power loads onto plasma‐facing components, particularly the divertor targets. Impurity seeding is an essential strategy for increasing the radiation losses and thereby reducing the heat load on the targets.
Hang Si, Gakushi Kawamura, Nobuyuki Asakura, Kazuo Hoshino, Haruki Seto, Yoshiteru Sakamoto, Masatoshi Yagi   +6 more
wiley   +1 more source

Investigation of helium exhaust dynamics at the ASDEX Upgrade tokamak with full-tungsten wall

Nuclear Fusion, 2023
An efficient removal of He ash by active pumping in future fusion devices is necessary to avoid fuel dilution and not degrade the core confinement properties. Therefore, a deep understanding of the underlying physics mechanisms is mandatory.
A. Zito, M. Wischmeier, A. Kappatou, A. Kallenbach, F. Sciortino, V. Rohde, K. Schmid, E.T. Hinson, O. Schmitz, M. Cavedon, R.M. McDermott, R. Dux, M. Griener, U. Stroth, the ASDEX Upgrade Team   +14 more
doaj   +1 more source

Optimization of tungsten castellated structures for the ITER divertor [PDF]

Journal of Nuclear Materials, 2015
Abstract In ITER, the plasma-facing components (PFCs) of the first wall and the divertor armor will be castellated to improve their thermo-mechanical stability and to limit forces due to induced currents. The fuel accumulation in the gaps may significantly contribute to the in-vessel fuel inventory.
Litnovsky, A., Hellwig, M., Matveev, D., Komm, M., van den Berg, M., De Temmerman, G., Rudakov, D., Ding, F., Luo, G.N., Krieger, K., Sugiyama, K., Pitts, R.A., Petersson, P.   +12 more
openaire   +3 more sources