Results 151 to 160 of about 585 (174)

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

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

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

Nuclear analysis of the ITER full-tungsten divertor

Fusion Engineering and Design, 2013
Abstract This paper presents the nuclear analysis performed for the ITER full-tungsten divertor using the MCNP-5 Monte Carlo Code in a 3-D geometry. A detailed model of the geometry of the divertor based on the last design specifications has been integrated into the latest ITER MCNP model.
R. Villari, V. Barabash, F. Escourbiac, L. Ferrand, T. Hirai, V. Komarov, M. Loughlin, M. Merola, F. Moro, L. Petrizzi, S. Podda, E. Polunovsky, G. Brolatti   +12 more
openaire   +2 more sources

Development of tungsten and tungsten alloys for DEMO divertor applications via MIM technology

Journal of Nuclear Materials, 2013
Abstract This paper is an overview of the very first results obtained on pure tungsten (W) and oxide dispersed strengthened (ODS) W alloys produced by the Metal Injection Molding (MIM) technique for fusion applications. An extensive mechanical and physical characterization was performed, together with microstructural material investigation.
D.T. Blagoeva, J. Opschoor, J.G. van der Laan, C. Sârbu, G. Pintsuk, M. Jong, T. Bakker, P. Ten Pierick, H. Nolles   +8 more
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

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

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

Evaluation of Marangoni convection and free surface velocity of molten tungsten for tungsten divertor

Fusion Engineering and Design, 2019
Abstract A tungsten divertor will be repetitively subjected to high heat fluxes when plasma disruptions or edge-localized modes occur, and the surface of the divertor will be molten and solidified repeatedly during the reactor operation. In an experiment, a tungsten specimen was irradiated by laser, and the center of the irradiated area was found to ...
Kohei Hamaguchi, Eiji Hoashi, Takafumi Okita, Kenzo Ibano, Yoshio Ueda   +4 more
openaire   +1 more source