High-temperature engineering test reactor

{{Short description|Research reactor in Ōarai, Ibaraki, Japan}} {{more citations needed|date=April 2024}} {{Use dmy dates|date=May 2024}} The '''high-temperature engineering test reactor''' ('''HTTR''') is a graphite-[[neutron moderator|moderated]] gas-cooled [[research reactor]] in [[Ōarai, Ibaraki]], Japan operated by the [[Japan Atomic Energy Agency]]. It uses long hexagonal fuel assemblies, unlike the competing [[pebble bed reactor]] designs.

HTTR first reached its full design power of 30 MW (thermal) in 1999. Other tests have shown that the core can reach temperatures sufficient for [[hydrogen production]] via the [[sulfur-iodine cycle]].<ref>{{cite news |last1=Hanawa |first1=Kazunari |title=Japan eyes hydrogen production using next-gen nuclear reactor |url=https://asia.nikkei.com/Business/Energy/Japan-eyes-hydrogen-production-using-next-gen-nuclear-reactor |access-date=4 April 2024 |work=Nikkei Asia |date=4 April 2024}}</ref>

==Technical details== The primary coolant is helium gas at a pressure of about {{convert|4|MPa}}, the inlet temperature of {{convert|395|°C}}, and the outlet temperature of {{convert|850–950|°C}}. The fuel is uranium oxide ([[Enriched uranium|enriched]] to an average of about 6%).

==See also== *[[Very-high-temperature reactor]] *[[Hydrogen economy]]

==References== {{Reflist}}

==External links== * [https://www.jaea.go.jp/04/o-arai/nhc/en/faq/httr.html HTTR] at the [[JAEA]] website.

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[[Category:Graphite moderated reactors]] [[Category:Nuclear technology in Japan]] [[Category:Ōarai, Ibaraki]]

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