Results 221 to 230 of about 32,282 (260)

Development of Carbon Materials and Plasma Facing Components for ITER

Physica Scripta, 2004
A significant R&D effort was carried out in EU to develop suitable CFC materials with a three-directional fibre structure. The main goal was to obtain a high thermal conductivity, which is required to remove the expected heat load with a sacrificial thickness of at least 15?20 mm, with a proper balance of the mechanical properties.
Merola, M., Wu, C., EU ITER Participating Team   +2 more
openaire   +2 more sources

The Design of Actively Cooled Plasma-Facing Components

Physica Scripta, 2001
In future fusion devices, like in the stellarator Wendelstein 7-X, the target plates of the divertor will be exposed to heat loads up to power densities of 10 MW/m2 for 1000 s. For this purpose actively cooled target elements with an internal coolant flow return, made of 2-D CFC armor tiles brazed onto a two tube cooling structure were developed and ...
Scheerer, M., Bolt, H., Gervash, A., Linke, J., Smid, I.   +4 more
openaire   +2 more sources

Fatigue life of the plasma-facing components in PULSAR

Fusion Engineering and Design, 1995
Abstract The PULSAR project is a multi-institutional effort to determine the advantages that can be gained by building a tokamak with an entirely inductive current drive. This machine, which would operate in a pulsed mode, would feature reduced capital and operating costs compared with steady-state devices requiring complex current drive systems ...
Jeffrey A Crowell, James P Blanchard
openaire   +1 more source

Armour Materials for the ITER Plasma Facing Components

Physica Scripta, 1999
The selection of the armour materials for the Plasma Facing Components (PFCs) of the International Thermonuclear Experimental Reactor (ITER) is a trade-off between multiple requirements derived from the unique features of a burning fusion plasma environment.
Barabash, V., Federici, G., Matera, R., Raffray, A., ITER-Home-Teams   +4 more
openaire   +2 more sources

Beryllium plasma-facing components: JET experience

Fusion Engineering and Design, 1997
Abstract JET has accumulated practical experience of plasma operation in both limiter and divertor configurations using massive beryllium plasma-facing components. These latter have shown evidence, even after a very short operational phase, for localised melting of the beryllium surface.
E.B Deksnis, A.T Peacock, H Altmann, C Ibbot, H.D Falter   +4 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

RUNAWAY ELECTRONS ON PLASMA FACING COMPONENTS

1993
Runaway electrons can cause severe damage to plasma facing components of large tokamaks. The designs proposed for the first wall and divertor of the next large fusion experiment, ITER (International Thermonuclear Experimental Reactor), are investigated. Energies of up to 300 MeV per electron and surface energy depositions of 30 MJ/m2 are assumed.
openaire   +2 more sources

ITER plasma facing components, design and development

Fusion Engineering and Design, 1991
Abstract The paper summarizes the collaborative effort of the ITER Conceptual Design Activity (CDA) on Plasma Facing Components (PFC) which focused on the following main tasks: (a) the definition of basic design concepts for the First Wall (FW) and Divertor Plates (DP), (b) the analysis of the performance and likely lifetime of these PFC designs ...
G. Vieider, A. Cardella, M. Akiba, R. Matera, R. Watson   +4 more
openaire   +1 more source

Development of beryllium bonds for plasma-facing components

Journal of Nuclear Materials, 1992
This study concerns the techniques of bonding beryllium to both structural material (AISI 316 SS) and heat sink material (copper and DS-copper) plates, and the characterization of the bonding material obtained. Conventional bonding techniques for joining Be to SS and copper using brazing alloys were first investigated, The best, result was obtained ...
E. Franconi, G.C. Ceccotti, L. Magnoli
openaire   +2 more sources

Advances in tungsten-armored plasma facing components

Proceedings of the 19th IEEE/IPSS Symposium on Fusion Engineering. 19th SOFE (Cat. No.02CH37231), 2003
High-Z armor is appropriate for use on plasma facing components (pfcs) subjected to very high heat loads and low plasma edge temperatures. During the past several years much progress was made on the development of tungsten rod armor bonded to water-cooled heatsinks.
D.L. Youchison, R.E. Nygren, J.S. O'Dell, J.M. McDonald, T.J. Lutz   +4 more
openaire   +1 more source