High-temperature engineering test reactor

Coordinates: 36°15′58.8″N 140°32′50.8″E / 36.266333°N 140.547444°E / 36.266333; 140.547444
From Wikipedia, the free encyclopedia

This is an old revision of this page, as edited by Yaris678 (talk | contribs) at 16:25, 27 February 2024 (→‎top: As per the article name, the full name of the rector includes "engineering" even though the abbreviation is HTTR. See the linked page of the JAEA website). The present address (URL) is a permanent link to this revision, which may differ significantly from the current revision.

The high-temperature engineering test reactor (HTTR) is a graphite-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.

Technical details

The primary coolant is helium gas at a pressure of about 4 megapascals (580 psi), the inlet temperature of 395 °C (743 °F), and the outlet temperature of 850–950 °C (1,560–1,740 °F). The fuel is uranium oxide (enriched to an average of about 6%).

See also

External links

36°15′58.8″N 140°32′50.8″E / 36.266333°N 140.547444°E / 36.266333; 140.547444