March 13, 2013
Journal Article

Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

Abstract

Tungsten materials are candidates for plasma facing components for ITER and DEMO because of their superior thermophysical properties. Knowledge and strategies to improve properties of tungsten-based materials are still under development, as they are not a common structural material such as steel. Consequently, several activities have started in Europe, Japan, USA and China. Research is directed towards manufacturing of new materials based on alloying, microstructure stabilizing and composite formation involving improved processing steps. Beside experimental analyses, work also focuses on computational treatment of open questions, supporting the development of better tungsten materials. Assuming the availability of an ideal material that is ready to use, there remain the questions of inherent safety, the joining of tungsten to steel and the influence of radiation damage. These are topics of increasing interest when the material comes to application.

Revised: March 12, 2014 | Published: March 13, 2013

Citation

Wurster S., N. Baluc, M. Battabyal, T. Crosby, J. Du, C. Garcia-Rosales, and A. Hasegawa, et al. 2013. Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials. Journal of Nuclear Materials 442, no. 1-3:S181-S189. PNNL-SA-83320. doi:10.1016/j.jnucmat.2013.02.074