Results 251 to 260 of about 35,628 (303)

Plasma facing components of EAST

Fusion Engineering and Design, 2010
Abstract EAST plasma facing components (PFCs) have the function of protecting the vacuum vessel, heating systems and diagnostic components from the plasma particles and heat loads, and also additional to this particles and heat loads handling.
Y T Song, S M Wang, X M Wang
exaly   +2 more sources

A new vision of plasma facing components

Fusion Engineering and Design, 2016
Abstract This paper advances a vision for plasma facing components (PFCs) that includes the following points. The solution for plasma facing materials likely consists of engineered structures in which the layer of plasma facing material (PFM) is integrated with an engineered structure that cools the PFM and may also transition with graded composition.
D L Youchison, Brian D Wirth, Lance L Snead   +2 more
exaly   +3 more sources

Net plasma facing components

Fusion Engineering and Design, 1989
Abstract The progress in the design and development of the first wall (FW) and divertor plates (DP) for the Next European Torus (NET) are summarized, highlighting the assumed main operating conditions, material choices, design options and their analysis as well as associated manufacturing studies and the ongoing testing programme.
G. Vieider, M. Harrison, F. Moons
openaire   +2 more sources

Erosion of plasma-facing components in ITER

Fusion Engineering and Design, 2002
Abstract Erosion of ITER plasma-facing components (PFCs) is analysed with a strike-point carbon divertor target and metallic walls (Be in the main chamber, and W divertor baffles), for a ‘semi-detached’ edge plasma regime, with Type I ELMs and off-normal events (e.g. disruptions). This paper builds on earlier studies [J. Nucl. Mater.
Federici, G., Würz, H., Janeschitz, G., Tivey, R.   +3 more
openaire   +3 more sources

Tritium in plasma facing components

Fusion Engineering and Design, 2001
Recent results on measurements of tritium and other hydrogen isotopes in first wall materials of large tokamaks are discussed and evaluated. Data on the in situ and ex situ release of tritium from plasma facing components under different conditions are assessed.
Penzhorn, R. D., Coad, J. P., Bekris, N., Doerr, L., Friedrich, M., Pilz, W.   +5 more
openaire   +2 more sources

ITER plasma-facing components

Fusion Engineering and Design, 2010
Abstract The ITER plasma-facing components directly face the thermonuclear plasma and include the divertor, the blanket and the test blanket modules with their corresponding frames. The divertor is located at the bottom of the plasma chamber and is aimed at exhausting the major part of the plasma thermal power (including alpha power) and at ...
Mario Merola, D. Loesser, A. Martin, P. Chappuis, R. Mitteau, V. Komarov, R.A. Pitts, S. Gicquel, V. Barabash, L. Giancarli, J. Palmer, M. Nakahira, A. Loarte, D. Campbell, R. Eaton, A. Kukushkin, M. Sugihara, F. Zhang, C.S. Kim, R. Raffray, L. Ferrand, D. Yao, S. Sadakov, A. Furmanek, V. Rozov, T. Hirai, F. Escourbiac, T. Jokinen, B. Calcagno, S. Mori   +29 more
openaire   +1 more source

Plasma-sprayed coatings for plasma-facing components

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
High-Z materials such as tungsten and low-Z materials such as boron carbide are of significance as internal coatings for plasma erosion protective purposes in nuclear fusion devices. Both materials were processed by plasma spraying. The given substrate for boron carbide was steel, where the dominant problem is the internal stress in the layer, which ...
W. Mallener, R. Duwe, K.-H. Rauwald
openaire   +1 more source

Design of the ITER EDA plasma facing components

Fusion Engineering and Design, 1998
Abstract The design of the plasma facing components (PFC) in ITER has evolved with the detailed design of the reactor. The structures exposed to the plasma have different requirements according to their functions. The primary wall, surrounding most of the plasma along the last closed magnetic surface, is exposed to a moderate heat flux (0.5 MW m−2 ...
Cardella, A., Abdou, M., Chiocchio, S., et al., Ioki, K., Parker, R., Lodato, A., Tivey, R., Bruno, L., Jakeman, R., Mohri, K., Raffray, R., Vieider, G., Lorenzetto, B., et al.   +14 more
openaire   +2 more sources

Research on plasma-facing component materials

Journal of Nuclear Materials, 1996
Abstract An irradiation target chamber with rotatable table and cooling systems and a set of quadrupole magnetic lenses associated with the 14 MeV, short-pulse electron linear accelerator was used to irradiate high heat flux materials. The electron gamma shower simulation code (EGS4) was modified to calculate the displacement atom concentration ...
Jinnan Yu, Yiren Chen, Yuzhu Wang, Wen Zhang, Shuyan Xu, Tetsuji Noda   +5 more
openaire   +1 more source

On “bubbly” structures in plasma facing components

Journal of Nuclear Materials, 2013
Abstract The theoretical model of “fuzz” growth describing the main features observed in experiments is discussed. This model is based on the assumption of enhancement of plasticity of tungsten containing significant fraction of helium atoms and clusters.
S.I. Krasheninnikov, R.D. Smirnov
openaire   +1 more source