scholarly journals High Heat Flux Performance of Plasma Facing Materials and Components under Service Conditions in Future Fusion Reactors

2012 ◽  
Vol 61 (2T) ◽  
pp. 246-255 ◽  
Author(s):  
Jochen Linke
Keyword(s):  
Heat Flux ◽  
High Heat ◽  
Fusion Reactors ◽  
High Heat Flux ◽  
Service Conditions ◽  
Plasma Facing Materials

scholarly journals Development of advanced high heat flux and plasma-facing materials

2017 ◽  
Vol 57 (9) ◽  
pp. 092007 ◽  
Author(s):  
Ch. Linsmeier ◽  
M. Rieth ◽  
J. Aktaa ◽  
T. Chikada ◽  
A. Hoffmann ◽  
...  
Keyword(s):  
Heat Flux ◽  
High Heat ◽  
High Heat Flux ◽  
Plasma Facing Materials

High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities

2007 ◽  
Vol 367-370 ◽  
pp. 1422-1431 ◽  
Author(s):  
J. Linke ◽  
F. Escourbiac ◽  
I.V. Mazul ◽  
R. Nygren ◽  
M. Rödig ◽  
...  
Keyword(s):  
Heat Flux ◽  
High Heat ◽  
High Heat Flux ◽  
Plasma Facing Materials

scholarly journals Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

2014 ◽  
Vol 455 (1-3) ◽  
pp. 277-291 ◽  
Author(s):  
D. Stork ◽  
P. Agostini ◽  
J.L. Boutard ◽  
D. Buckthorpe ◽  
E. Diegele ◽  
...  
Keyword(s):  
Heat Flux ◽  
Power Plant ◽  
High Heat ◽  
High Heat Flux ◽  
Fusion Power ◽  
Fusion Power Plant ◽  
Plasma Facing Materials ◽  
Near Term ◽  
Structural High ◽  
The Eu

High-heat-flux experiment on plasma-facing materials by electron beam irradiation

1994 ◽  
Vol 212-215 ◽  
pp. 1323-1328 ◽  
Author(s):  
K. Tokunaga ◽  
K. Matsumoto ◽  
Y. Miyamoto ◽  
T. Muroga ◽  
N. Yoshida
Keyword(s):  
Heat Flux ◽  
Electron Beam ◽  
Electron Beam Irradiation ◽  
High Heat ◽  
High Heat Flux ◽  
Beam Irradiation ◽  
Plasma Facing Materials

Development of Functionally Graded Coating Based Plasma Facing Materials for Fusion Reactor

2010 ◽  
Vol 63 ◽  
pp. 383-391
Author(s):  
Chang Chun Ge ◽  
Shuang Quan Guo ◽  
Yun Biao Feng ◽  
Zhang Jian Zhou ◽  
Juan Du ◽  
...  
Keyword(s):  
Heat Flux ◽  
Plasma Spray ◽  
Vapor Deposition ◽  
Fusion Reactor ◽  
High Heat ◽  
Functionally Graded ◽  
Atmospheric Plasma ◽  
High Heat Flux ◽  
Tungsten Coating ◽  
Plasma Facing Materials

Different coating technologies, such as plasma spray (PS), physical vapor deposition (PVD) and chemical vapor deposition (CVD), which can fabricate the PFM and join it to heat sink materials simultaneously, were applied for the fabrication of plasma facing materials (PFM) in fusion reactor. In the Institute of Nuclear Materials, University of Science and Technology Beijing (USTB), the concept of functionally graded materials (FGM) was adopted to fabricate coatings for effectively alleviating the thermal stress generated between coatings and the substrate materials under high heat flux loading (5~20 MW/m2). In the last several years, functionally graded coatings, including B4C/Cu, W/Cu and Mo/Cu systems were successfully fabricated by atmospheric plasma spray (APS). Characterization of coatings was performed in order to assess microstructure, mechanical properties and high heat flux properties of the FGM coatings. Furthermore, a high thick tungsten coating with 4 mm on copper – chromium - zirconium (Cu, Cr, Zr) alloy substrates was fabricated by APS. The porosity of the coating is less than 2% while mean tensile strength of the coating is about 7 MPa. However, the content of oxygen in the coating is about 6 wt% by energy dispersive spectrum (EDS) analysis, thus further optimization is necessary.

Bonding and Interfaces and their Thermo-Mechanical Performance on the Example of Plasma Facing Divertor Components for Thermo-Nuclear Fusion Reactors

2008 ◽  
Vol 59 ◽  
pp. 31-35
Author(s):  
Arno Plankensteiner ◽  
Bernhard Tabernig
Keyword(s):  
Heat Flux ◽  
Finite Element ◽  
Fracture Mechanics ◽  
Nuclear Fusion ◽  
High Heat ◽  
Fusion Reactors ◽  
High Heat Flux ◽  
Loading Conditions ◽  
Micro Scale ◽  
Macro Scale

The optimization of CFC/Cu-interfaces for plasma facing divertor components in thermo-nuclear fusion reactors is proposed and demonstrated via an integrative numerical-experimental approach mainly comprising a macro-scale to micro-scale finite element modeling technique together with fracture mechanics tests. Results obtained by finite element analyses of real-scale CFC flat tile divertor components under high heat flux loading conditions are verified by the findings of tests in an ion beam high heat flux facility. From the macro-scale FE models of the full component the loading conditions are derived for micro-scale FE models that incorporate principal details of the micro-structured CFC/Cu-interface thus allowing to capture explicitly locally acting dissipative mechanisms which in turn at the macro-scale in fracture mechanics experiments increase the fracture toughness of the CFC/Cu-interface.

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