Results 211 to 220 of about 32,282 (260)

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

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

Damage modelling in plasma facing components

Journal of Nuclear Materials, 2009
Abstract The plasma facing components of controlled fusion devices are submitted to high heat fluxes in operating conditions (from 10 to 20 MW/m 2 ). These components are made of a carbon/carbon composite tile bonded to a copper alloy heat sink. Due to the thermal expansion mismatch between the composite and the copper alloy, significant stresses may
E. Martin, G. Camus, J. Schlosser, G. Chevet   +3 more
openaire   +1 more source

Tritium in plasma facing components

Nuclear Fusion, 1992
Report on the Workshop held after the 10th PSI Conference, Livermore, California, United States of America, 6-7 April 1992.
openaire   +1 more source

Effect of disruptions on plasma-facing components

Proceedings of 16th International Symposium on Fusion Engineering, 2002
Erosion of plasma-facing components during disruptions is a limiting factor in the design of large tokamaks like ITER. During a disruption, much of the stored thermal energy of the plasma will be dumped onto divertor plates, resulting in local heat fluxes, which may exceed 100 GW/m/sup 2/ over a period of about 0.1-1.0 msec.
J.G. Gilligan, M.A. Bourham, E.C. Tucker
openaire   +1 more source

Development of plasma facing components at JAERI

Fusion Engineering and Design, 1991
The development and design of the divertor plate in JAERI are presented. Small divertor models are fabricated and tested in an electron beam heating facility in the JAERI. Typical heat load is 10 MW/m2. The divertor models consist of CFC or isotropic graphite/Cu bonded structures. A twisted tape is inserted to enhance heat transfer.
M. Akiba, H. Takatsu, T. Kuroda, H. Hashizume, M. Araki, M. Dairaku, H. Ise, S. Suzuki, S. Tanaka, K. Yokoyama, M. Seki   +10 more
openaire   +1 more source