Summary
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.[1]
Technical details edit
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 edit
References edit
- ^ Hanawa, Kazunari (4 April 2024). "Japan eyes hydrogen production using next-gen nuclear reactor". Nikkei Asia. Retrieved 4 April 2024.
External links edit
- HTTR at the JAEA website.
36°15′58.8″N 140°32′50.8″E / 36.266333°N 140.547444°E