Editing Large Helical Device (section)

==History==
* Design finalized 1987
* Start of construction 1990
* Plasma operations from 1998
* Neutral beam injection of 3 MW was used in 1999.<ref>{{cite journal |title=Plasma confinement studies in LHD |journal=Nuclear Fusion |volume=39 |issue=11Y |pages=1659–1666 |year=1999 |quote=Heating by NBI of 3 MW produced plasmas with a fusion triple product of 8 × 10<sup>18</sup>m<sup>−3</sup> keV s at a magnetic field strength of 1.5 T. An electron temperature of 1.5 keV and an ion temperature of 1.1 keV were achieved simultaneously at a line averaged electron density of 1.5 × 10<sup>19</sup> m<sup>−3</sup> |doi=10.1088/0029-5515/39/11Y/305 |last1=Fujiwara |first1=M. |last2=Yamada |first2=H. |last3=Ejiri |first3=A. |last4=Emoto |first4=M. |last5=Funaba |first5=H. |last6=Goto |first6=M. |last7=Ida |first7=K. |last8=Idei |first8=H. |last9=Inagaki |first9=S. |last10=Kado |first10=S. |last11=Kaneko |first11=O. |last12=Kawahata |first12=K. |last13=Kobuchi |first13=T. |last14=Komori |first14=A. |last15=Kubo |first15=S. |last16=Kumazawa |first16=R. |last17=Masuzaki |first17=S. |last18=Minami |first18=T. |last19=Miyazawa |first19=J. |last20=Morisaki |first20=T. |last21=Morita |first21=S. |last22=Murakami |first22=S. |last23=Muto |first23=S. |last24=Mutoh |first24=T. |last25=Nagayama |first25=Y. |last26=Nakamura |first26=Y. |last27=Nakanishi |first27=H. |last28=Narihara |first28=K. |last29=Nishimura |first29=K. |last30=Noda |first30=N. |bibcode=1999NucFu..39.1659F |s2cid=250824691 |display-authors=29 }}</ref>
* In 2005 it maintained a plasma for 3,900 seconds.<ref>[http://iopscience.iop.org/article/10.1088/1742-6596/25/1/024 ''Achievement of One Hour Discharge with ECH on LHD'' 2005]</ref>
* In 2006 a new helium cooler was added. Using the new cooler, by 2018 a total of 10 long term operations have been achieved, reaching a maximum power level of 11.833 kA.<ref>{{Cite journal|last=Hamaguchi, Imagawa, Obana, Yanagi and Mito|date=2018|title=Operations of the Helium Subcooling System for the LHD HelicalCoils during Ten Plasma Experimental Campaigns|url=http://www.jspf.or.jp/PFR/PDF2018/pfr2018_13-3405057|journal=Plasma and Fusion Research|volume=13|pages=3405057|doi=10.1585/pfr.13.3405057|bibcode=2018PFR....1305057H |doi-access=free}}</ref>
* To aid public acceptance, an exhaust system was designed to catch and filter the radioactive [[tritium]] the fusion process produces.<ref>{{Cite web|url=https://www.researchgate.net/publication/322866554|title=Design and commissioning of the exhaust detritiation system for the Large Helical Device|website=ResearchGate|language=en|access-date=2019-03-04}}</ref>
{{expand section|date=March 2018}}