High-temperature_engineering_test_reactor

High-temperature engineering test reactor

High-temperature engineering test reactor

Research reactor in Ōarai, Ibaraki, Japan

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

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

References

  1. [1]
    Hanawa, Kazunari (4 April 2024). "Japan eyes hydrogen production using next-gen nuclear reactor". Nikkei Asia. Retrieved 4 April 2024.

36°15′58.8″N 140°32′50.8″E


Stub icon

This article about a Japanese building- or structure-related topic is a stub. You can help Wikipedia by expanding it.

Stub icon

This article about nuclear power and nuclear reactors for power generation is a stub. You can help Wikipedia by expanding it.
Share this article:

This article uses material from the Wikipedia article High-temperature_engineering_test_reactor, and is written by contributors. Text is available under a CC BY-SA 4.0 International License; additional terms may apply. Images, videos and audio are available under their respective licenses.