The High-Temperature Gas Cooled Reactor (HTGR) is able to offer
high-temperature heat, high thermal efficiency and inherent safety
features.
Research and development on the HTGR were started in the Japan
Atomic Energy Research Institute (JAERI) in 1967. The High-Temperature
Engineering Test Reactor (HTTR) Project, established in 1987,
in acordance with The Long Term Plan of Developing Nuclear Power
in Japan. This project performs fundamental research and development,
such as research on graphite, fuel, etc., as seen in Fig. 5-1.
The objectives of the HTTR project are to establish and upgrade
the technology basis for an advanced HTGR and to conduct basic
research at high temperatures and irradiation through the construction
and operation of the HTTR. The basic research and irradiation
tests at high-temperature (400 ~ 1000 degrees cent.) using the HTTR are contributing to the advancement
of irradiation research and to innovative basic research for the
future. Demonstrations of the inherent safety features of the
HTGR and the utilization of high-temperature energy will also
be performed with the HTTR. The expanded use of nuclear energy
for high-temperature nonelectric applications, e.g., hydrogen
production, enhances the diversity of energy sources and secures
the stability of the supply of energy. The proposed themes of
basic research are shown in Fig. 5-2. These basic research themes
are expected to provide opportunities for radical innovations
for future technologies. |
