TY - JOUR
T1 - High-temperature continuous operation of the HTTR
AU - Takamatsu, Kuniyoshi
AU - Sawa, Kazuhiro
AU - Kunitomi, Kazuhiko
AU - Hino, Ryutaro
AU - Ogawa, Masuro
AU - Komori, Yoshihiro
AU - Nakazawa, Toshio
AU - Iyoku, Tatsuo
AU - Fujimoto, Nozomu
AU - Nishihara, Tetsuo
AU - Shinozaki, Masayuki
N1 - Copyright:
Copyright 2012 Elsevier B.V., All rights reserved.
PY - 2011/12
Y1 - 2011/12
N2 - 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.
AB - 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.
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U2 - 10.3327/taesj.J11.020
DO - 10.3327/taesj.J11.020
M3 - Article
AN - SCOPUS:84856450655
SN - 1347-2879
VL - 10
SP - 290
EP - 300
JO - Transactions of the Atomic Energy Society of Japan
JF - Transactions of the Atomic Energy Society of Japan
IS - 4
ER -
