Tungsten response to transient heat loads generated by laser pulses

Author

Harilal, S.S. ; Suslova, A. ; Et-Atwani, O. ; Farid, N. ; Hassanein, A.

Author_Institution

Center for Mater. Under Extreme Environ., Purdue Univ., West Lafayette, IN, USA

fYear

2014

fDate

25-29 May 2014

Firstpage

1

Lastpage

1

Abstract

Tungsten (W) has been selected as a plasma-facing component (PFC) material in the activated phase of ITER. High melting point and thermal conductivity and low erosion rate and low tritium inventory are the major advantages of W material, which makes it suitable for plasma fusion technology. However, ductile-to-brittle transition is also a major drawback of W, which could produce large macroscopic particles as well as small dust particles. The emission of dust particles from W are found to persist for longer duration compared to plasma lifetime with velocities of several tens m/s. The lifetime of the PFCs also depends on ELMs, VDEs, disruptions and runaway electrons.

Keywords

Tokamak devices; ductile-brittle transition; melting point; plasma light propagation; plasma toroidal confinement; plasma-wall interactions; thermal conductivity; tungsten; ELM; ITER; VDE; W; ductile-to-brittle transition; dust particles; high melting point; laser pulse generation; low erosion rate; low tritium inventory are; macroscopic particles; plasma disruption; plasma fusion technology; plasma velocity; plasma-facing component material; runaway electrons; thermal conductivity; transient heat loads; tungsten response; Heating; Laser applications; Materials; Plasmas; Power lasers; Surface morphology; Transient analysis;

fLanguage

English

Publisher

ieee

Conference_Titel

Plasma Sciences (ICOPS) held with 2014 IEEE International Conference on High-Power Particle Beams (BEAMS), 2014 IEEE 41st International Conference on

Conference_Location

Washington, DC

Print_ISBN

978-1-4799-2711-1

Type

conf

DOI

10.1109/PLASMA.2014.7012277

Filename

7012277