Editing Tungsten (section)

=== Fusion power ===
Due to its high melting point and good erosion resistance, tungsten is a lead candidate for the most exposed sections of the plasma-facing inner wall of [[nuclear fusion]] [[Fusion power|reactors]]. Tungsten, as a plasma-facing component material, features exceptionally low [[tritium]] retention through co-deposition and implantation, which enhances safety by minimizing radioactive inventory, improves fuel efficiency by making more fuel available for fusion reactions, and supports operational continuity by reducing the need for frequent fuel removal from surfaces.<ref>{{cite journal |last1=Roth |first1=Joachim |last2=Tsitrone |first2=E. |last3=Loarte |first3=A. |last4=Loarer |first4=Th. |last5=Counsell |first5=G. |last6=Neu |first6=R. |last7=Philipps |first7=V. |last8=Brezinsek |first8=S. |last9=Lehnen |first9=M. |last10=Coad |first10=P. |last11=Grisolia |first11=Ch. |last12=Schmid |first12=K. |last13=Krieger |first13=K. |last14=Kallenbach |first14=A. |last15=Lipschultz |first15=B. |last16=Doerner |first16=R. |last17=Causey |first17=R. |last18=Alimov |first18=V. |last19=Shu |first19=W. |last20=Ogorodnikova |first20=O. |last21=Kirschner |first21=A. |last22=Federici |first22=G. |last23=Kukushkin |first23=A. |title=Recent analysis of key plasma wall interactions issues for ITER |journal=Journal of Nuclear Materials |date=2009 |volume=390-391 |pages=1–9 |doi=10.1016/j.jnucmat.2009.01.037 |bibcode=2009JNuM..390....1R |hdl=11858/00-001M-0000-0026-F442-2 |url=https://www.sciencedirect.com/science/article/pii/S0022311509000506 |issn=0022-3115|hdl-access=free }}</ref> It will be used as the [[plasma-facing material]] of the [[divertor]] in the [[ITER]] reactor,<ref>{{Cite journal|last1=Pitts|first1=R. A.|last2=Carpentier|first2=S.|last3=Escourbiac|first3=F.|last4=Hirai|first4=T.|last5=Komarov|first5=V.|last6=Lisgo|first6=S.|last7=Kukushkin|first7=A. S.|last8=Loarte|first8=A.|last9=Merola|first9=M.|last10=Sashala Naik|first10=A.|last11=Mitteau|first11=R.|date=2013-07-01|title=A full tungsten divertor for ITER: Physics issues and design status|journal=Journal of Nuclear Materials|series=Proceedings of the 20th International Conference on Plasma-Surface Interactions in Controlled Fusion Devices|language=en|volume=438|pages=S48–S56|doi=10.1016/j.jnucmat.2013.01.008|bibcode=2013JNuM..438S..48P|issn=0022-3115}}</ref> and is currently in use in the [[Joint European Torus|JET]] test reactor.