Improvement of Analysis Technology for High Temperature Gas-Cooled Reactor by Using Data Obtained in High Temperature Engineering Test Reactor

Abstract

The Very High Temperature Reactor (VHTR) system, which is one of generation IV reactors, is the high temperature gas-cooled reactor (HTGR) with capabilities of hydrogen production and high efficiency electricity generation. The High Temperature Engineering Test Reactor (HTTR) is the first HTGR in Japan. The HTTR achieved full power of 30MW at a reactor outlet coolant temperature of about 950 °C in April, 2004 during the "rise-to-power tests" confirming the reactor performance. The safety demonstration tests by using the HTTR started from 2002 and are under going to demonstrate inherent safety features of HTGRs. The experimental data obtained in these tests are inevitable to design the VHTR with high cost performance. The analytical models validated through these tests in the HTTR are applicable to precise simulation of an HTGR performance and can contribute to the research and development of the VHTR.

Development of a zero‐dimensional dynamic simulator of a power conversion system with a high‐temperature gas reactor

“…The active core is 2.9 m in height and 2.3 in diameter providing a power density of 2.5 MW/cm 3 . 20,21 In Table 1, the plant operational parameters used in this work are presented.…”

“…The reactor can be operated in two different modes: the rated mode with an outlet coolant temperature of 850 C and high-temperature mode with an outlet temperature of 950 C. The reactor is intended not only for hydrogen production but also to provide experimental information for the HTGRs technology development. 20 In Table 2, the main features of the HTTR are presented.…”

“…Axial and radial view of the httr reactor core and main components20 [Colour figure can be viewed at wileyonlinelibrary.com] T A B L E 1 Plant operational parameters1 …”