Large Helical Device

<h2 id="history">History</h2>
<ul><li>Design finalized 1987</li>
<li>Start of construction 1990</li>
<li>Plasma operations from 1998</li>
<li>Neutral beam injection of 3 MW was used in 1999.<a class="footnote-ref" id="fnref:3" href="#fn:3"><sup>3</sup></a></li>
<li>In 2005 it maintained a plasma for 3,900 seconds.<a class="footnote-ref" id="fnref:4" href="#fn:4"><sup>4</sup></a></li>
<li>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.<a class="footnote-ref" id="fnref:5" href="#fn:5"><sup>5</sup></a></li>
<li>To aid public acceptance, an exhaust system was designed to catch and filter the radioactive <a href="/facts/Tritium/HWSa6EHy">tritium</a> the fusion process produces.<a class="footnote-ref" id="fnref:6" href="#fn:6"><sup>6</sup></a></li></ul>

<h2 id="see-also">See also</h2>
<ul><li><a href="/facts/Fusion_reactor/jyETSzm4">Fusion reactor</a></li>
<li><a href="/facts/National_Institutes_of_Natural_Sciences,_Japan/zK70YcfU">National Institutes of Natural Sciences, Japan</a></li></ul>

<h2 id="external-links">External links</h2>
<ul><li><a href="http://www.lhd.nifs.ac.jp"><i>Large Helical Device</i> Website</a> <a href="https://web.archive.org/web/20111015200716/http://www.lhd.nifs.ac.jp/">Archived</a> 2011-10-15 at the <a href="/facts/Wayback_Machine/nmQ3a6JC">Wayback Machine</a> good diagrams (worth archiving page)</li>
<li><a href="http://ncsx.pppl.gov/Physics/NSTT/Harris_Jan08r3.pdf">Super Dense Core plasmas in LHD. Harris. 2008</a> 16 slides. advanced - inc ballooning mode and future development options</li></ul>

<h2 id="references">References</h2>

<ol>
<li id="fn:1"><p>Morisaki, T; et al. (2013). "Initial experiments towards edge plasma control with a closed helical divertor in LHD". Nucl. Fusion. 53 (6): 063014. Bibcode:2013NucFu..53f3014M. doi:10.1088/0029-5515/53/6/063014. S2CID 122537627. <a href="https://iopscience.iop.org/article/10.1088/0029-5515/53/6/063014" target="_blank">https://iopscience.iop.org/article/10.1088/0029-5515/53/6/063014</a> <a href="#fnref:1" class="footnote-back-ref">↩</a></p></li>
<li id="fn:2"><p>Bader, Aaron; Effenberg, Florian; Hegna, Chris C. (December 6, 2018). "Progress in Divertor and Edge Transport Research for Stellarator Plasmas" (PDF). Archived from the original (PDF) on 2023-07-26. <a href="https://web.archive.org/web/20230726233025/www.jspf.or.jp/jspf_annual2018/JSPF35/pdf/S8-4.pdf" target="_blank">https://web.archive.org/web/20230726233025/www.jspf.or.jp/jspf_annual2018/JSPF35/pdf/S8-4.pdf</a> <a href="#fnref:2" class="footnote-back-ref">↩</a></p></li>
<li id="fn:3"><p>Fujiwara, M.; Yamada, H.; Ejiri, A.; Emoto, M.; Funaba, H.; Goto, M.; Ida, K.; Idei, H.; Inagaki, S.; Kado, S.; Kaneko, O.; Kawahata, K.; Kobuchi, T.; Komori, A.; Kubo, S.; Kumazawa, R.; Masuzaki, S.; Minami, T.; Miyazawa, J.; Morisaki, T.; Morita, S.; Murakami, S.; Muto, S.; Mutoh, T.; Nagayama, Y.; Nakamura, Y.; Nakanishi, H.; Narihara, K.; Nishimura, K.; et al. (1999). "Plasma confinement studies in LHD". Nuclear Fusion. 39 (11Y): 1659–1666. Bibcode:1999NucFu..39.1659F. doi:10.1088/0029-5515/39/11Y/305. S2CID 250824691. Heating by NBI of 3 MW produced plasmas with a fusion triple product of 8 × 1018m−3 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 × 1019 m−3 <a href="/wiki/Bibcode_(identifier)" target="_blank">/wiki/Bibcode_(identifier)</a> <a href="#fnref:3" class="footnote-back-ref">↩</a></p></li>
<li id="fn:4"><p>Achievement of One Hour Discharge with ECH on LHD 2005 <a href="http://iopscience.iop.org/article/10.1088/1742-6596/25/1/024" target="_blank">http://iopscience.iop.org/article/10.1088/1742-6596/25/1/024</a> <a href="#fnref:4" class="footnote-back-ref">↩</a></p></li>
<li id="fn:5"><p>Hamaguchi, Imagawa, Obana, Yanagi and Mito (2018). "Operations of the Helium Subcooling System for the LHD HelicalCoils during Ten Plasma Experimental Campaigns". Plasma and Fusion Research. 13: 3405057. Bibcode:2018PFR....1305057H. doi:10.1585/pfr.13.3405057.{{cite journal}}:  CS1 maint: multiple names: authors list (link) <a href="http://www.jspf.or.jp/PFR/PDF2018/pfr2018_13-3405057" target="_blank">http://www.jspf.or.jp/PFR/PDF2018/pfr2018_13-3405057</a> <a href="#fnref:5" class="footnote-back-ref">↩</a></p></li>
<li id="fn:6"><p>"Design and commissioning of the exhaust detritiation system for the Large Helical Device". ResearchGate. Retrieved 2019-03-04. <a href="https://www.researchgate.net/publication/322866554" target="_blank">https://www.researchgate.net/publication/322866554</a> <a href="#fnref:6" class="footnote-back-ref">↩</a></p></li>
</ol>

Large Helical Device open-in-new

Large Helical Device