High-temperature engineering test reactor: Difference between revisions
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The '''high-temperature test reactor''' ('''HTTR''') is a graphite-[[neutron moderator|moderated]] gas-cooled [[research reactor]] in [[Oarai, Ibaraki]], Japan operated by the [[Japan Atomic Energy Agency]]. It uses long hexagonal fuel assemblies, unlike the competing [[pebble bed reactor]] designs. |
The '''high-temperature test reactor''' ('''HTTR''') is a graphite-[[neutron moderator|moderated]] gas-cooled [[research reactor]] in [[Oarai, Ibaraki]], Japan operated by the [[Japan Atomic Energy Agency]]. It uses long hexagonal fuel assemblies, unlike the competing [[pebble bed reactor]] designs. |
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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]]. |
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]](see more [[sulfur-iodine cycle]]). |
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==Technical details== |
==Technical details== |
Revision as of 03:59, 23 May 2014
The high-temperature test reactor (HTTR) is a graphite-moderated gas-cooled research reactor in Oarai, 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(see more sulfur-iodine cycle).
Technical details
The primary coolant is helium gas at a pressure of about 4 MPa, the inlet temperature of 395 °C, and the outlet temperature of 850–950 °C. The fuel is uranium oxide (enriched to an average of about 6%).