Английская Википедия:High-temperature engineering test reactor
Шаблон:Unreferenced Шаблон:Use dmy dates Шаблон:Short description 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 Шаблон:Convert, the inlet temperature of Шаблон:Convert, and the outlet temperature of Шаблон:Convert. The fuel is uranium oxide (enriched to an average of about 6%).
See also
External links
Шаблон:Japan-struct-stub
Шаблон:Nuclear-power-stub
