DocumentCode :
1606773
Title :
Fusion materials science and technology research needs: Now and during the ITER era
Author :
Wirth, Brian D. ; Kurtz, R.J. ; Snead, Lance L.
Author_Institution :
Dept. of Nucl. Eng., Univ. of Tennessee, Knoxville, TN, USA
fYear :
2013
Firstpage :
1
Lastpage :
8
Abstract :
The plasma facing components, first wall and blanket systems of future tokamak-based fusion power plants arguably represent the single greatest materials engineering challenge of all time. Indeed, the United States National Academy of Engineering has recently ranked the quest for fusion as one of the top grand challenges for engineering in the 21st Century. These challenges are even more pronounced by the lack of experimental testing facilities that replicate the extreme operating environment involving simultaneous high heat and particle fluxes, large time varying stresses, corrosive chemical environments, and large fluxes of 14-MeV peaked fusion neutrons. This paper will review, and attempt to prioritize, the materials research and development challenges facing fusion nuclear science and technology into the ITER era and beyond to DEMO. In particular, the presentation will highlight the materials degradation mechanisms we anticipate to occur in the fusion environment, the temperature-displacment goals for fusion materials and plasma facing components and the near and long-term materials challenges required for both ITER, a fusion nuclear science facility and longer term ultimately DEMO.
Keywords :
Tokamak devices; fusion reactor blankets; plasma toroidal confinement; plasma-wall interactions; research and development; DEMO; ITER era; United States National Academy of Engineering; blanket systems; corrosive chemical environments; electron volt energy 14 MeV; experimental testing facilities; extreme operating environment; fusion environment; fusion material science and technology research; fusion neutrons; fusion nuclear science; fusion nuclear science facility; future tokamak-based fusion power plants; high heat flux; high particle flux; large time varying stresses; material degradation mechanisms; material engineering; material research and development; plasma facing components; temperature-displacment goals; Materials; Neutrons; Plasma temperature; Surface morphology; Surface treatment; Tungsten; He; fusion materials; neutron damage; plasma facing components; tritium;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
Type :
conf
DOI :
10.1109/SOFE.2013.6635413
Filename :
6635413
Link To Document :
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