High-temperature continuous operation of the HTTR

Kuniyoshi Takamatsu, Kazuhiro Sawa, Kazuhiko Kunitomi, Ryutaro Hino, Masuro Ogawa, Yoshihiro Komori, Toshio Nakazawa, Tatsuo Iyoku, Nozomu Fujimoto, Tetsuo Nishihara, Masayuki Shinozaki

Research output: Contribution to journalArticle

10 Citations (Scopus)

Abstract

A high-temperature gas-cooled reactor (HTGR) is a graphite-moderated and helium gas-cooled reactor. It is particularly attractive due to its capability of producing high-temperature helium gas, and its passive and inherent safety features. To enable nuclear energy application to a wide range of heat process industries, Japan Atomic Energy Agency (JAEA) has continued extensive effort for the development of the HTGR using the high-temperature engineering test reactor (HTTR), which is the first HTGR in Japan with a thermal power of 30 MW, and operates it at the site of the JAEA's Oarai Research and Development Center. The HTTR has successfully completed a full-power high-temperature (950°C) continuous operation for 50 days from January to March in 2010. Through this operation, the potential of a stable high-temperature heat supply to heat application systems, such as a hydrogen production system, was demonstrated. This paper presents the operation results including reactor characteristics.

Original languageEnglish
Pages (from-to)290-300
Number of pages11
JournalTransactions of the Atomic Energy Society of Japan
Volume10
Issue number4
DOIs
Publication statusPublished - Dec 1 2011
Externally publishedYes

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality

Fingerprint Dive into the research topics of 'High-temperature continuous operation of the HTTR'. Together they form a unique fingerprint.

  • Cite this

    Takamatsu, K., Sawa, K., Kunitomi, K., Hino, R., Ogawa, M., Komori, Y., Nakazawa, T., Iyoku, T., Fujimoto, N., Nishihara, T., & Shinozaki, M. (2011). High-temperature continuous operation of the HTTR. Transactions of the Atomic Energy Society of Japan, 10(4), 290-300. https://doi.org/10.3327/taesj.J11.020