Results 171 to 180 of about 96,750 (196)

Development of tungsten coatings for ITER divertor components

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 2002
The EU design of the ITER Divertor Wing envisages the use of tungsten as an armour because of its low sputter rate. To guarantee an adequate armour lifetime a minimum thickness of 5 mm is required. A promising technology to apply W as an armour for extended surfaces is the plasma spray process (PS).
Riccardi, B., Pizzuto, A., Bertamini, L., Vieider, G., et al.   +4 more
openaire   +2 more sources

Engineering Studies on the EAST Tungsten Divertor

IEEE Transactions on Plasma Science, 2014
Experimental advanced superconducting tokamak device is a D-shaped full superconducting tokamak with actively water cooled plasma facing components. To achieve long pulse and high βH-mode plasma, new plasma position and shape are calculated and optimized during the campaign of 2013-2014.
Zibo Zhou, Damao Yao, Lei Cao, Chao Liang, Changle Liu   +4 more
openaire   +1 more source

Assessment of radiological hazards of tungsten divertors

Fusion Engineering and Design, 1995
Abstract The radiological hazards of utilizing tungsten for divertors are investigated. The safety and environmental characteristics are assessed by an integrated approach coupling the evaluation of activation and tritium inventories, accident thermal transient analysis, mobilization of activated materials, and dose dispersion.
S.K. Ho, M.D. Lowenthal
openaire   +1 more source

Tungsten Coatings for Divertor Wings

International Thermal Spray Conference, 2001
Abstract For the coating of divertor wings, which in an adapted form may also be suitable for divertor targets, tungsten coatings were developed and optimized with respect to erosion and adhesion behaviour and tested in the Jülich JUDITH facility as well as in the St. Petersburg TSEFEY facility.
openaire   +1 more source

The dynamical mechanical properties of tungsten under compression at working temperature range of divertors

Journal of Nuclear Materials, 2016
In the divertor structure of ITER and EAST with mono-block module, tungsten plays not only a role of armor material but also a role of structural material, because electromagnetic (EM) impact will be exerted on tungsten components in VDEs or CQ The EM ...
Mao Xin, Y T Song, W X Li
exaly   +2 more sources

Divertor detachment operation in helium plasmas with ITER-like tungsten divertor in EAST

Plasma Science and Technology, 2022
Abstract Detachment in helium (He) discharges has been achieved in the EAST superconducting tokamak equipped with an ITER-like tungsten divertor. This paper presents the experimental observations of divertor detachment achieved by increasing the plasma density in He discharges.
Jianbin LIU, Lingyi MENG, Houyang GUO, Kedong LI, Jichan XU, Huiqian WANG, Guosheng XU, Fang DING, Ling ZHANG, Yanmin DUAN, Bin ZHANG, Lin YU, Ping WANG, Ang LI, Donggui WU, Rui DING, Liang WANG   +16 more
openaire   +1 more source

Fracture and Creep in an All-Tungsten Divertor for ARIES

Fusion Science and Technology, 2013
The ARIES project is currently proposing an all-tungsten divertor for their tokamak designs. In designing such a component, fracture will be a critical failure mechanism, due to the limited ductili...
James P. Blanchard, Carl Martin
openaire   +1 more source

Development of tungsten divertor components for ITER in Japan

Fusion Engineering and Design, 2018
Abstract The refined design of full-W ITER divertor outer vertical targets (OVT) has the combination of plasma-facing units (PFUs) variants with bevelled W monoblocks to prevent leading edge overheating. Full-length PFU prototypes have withstood against the repetitive heat load of 20MW/m2 and they met the requirements for W technologies qualification
K. Ezato, S. Suzuki, Y. Seki, T. Hirayama, H. Yamada, F. Escourbiac, T. Hirai   +6 more
openaire   +1 more source

Thermomechanical Analysis for an All-Tungsten ARIES Divertor

Fusion Science and Technology, 2015
AbstractThe ARIES team is currently proposing two tungsten divertor concepts for its tokamak designs and has performed extensive analyses to optimize their thermal and structural performance. Because of the high divertor operating temperatures and the low ductility of tungsten, thermal creep and fracture will be important failure mechanisms to consider.
James P. Blanchard, Carl Martin
openaire   +1 more source

Helium Jet-Cooled Tungsten Divertor Concept

2007 IEEE 22nd Symposium on Fusion Engineering, 2007
Helium cooled refractory metal heat sinks are being considered for the divertor sections for several fusion energy reactor concepts. Recent EU results have shown considerable promise for jet impingement type helium cooling techniques for high heat flux (HHF) applications. However, because of the small size of the "pin-like" units (1.5-2 cm diameter), a
J.S. O'Dell, A.R. Raffray
openaire   +1 more source