Performance test of HTTR

✍ Scribed by Shigeaki Nakagawa; Yukio Tachibana; Kuniyoshi Takamatsu; Shohei Ueta; Satoshi Hanawa

• Publisher: Elsevier Science
• Year: 2004
• Tongue: English
• Weight: 456 KB
• Volume: 233
• Category: Article
• ISSN: 0029-5493
• DOI: 10.1016/j.nucengdes.2004.08.027

✦ Synopsis

The high temperature gas-cooled reactor (HTGR) is particularly attractive due to its capability of producing high temperature helium gas and due to its inherent safety characteristics. The high temperature engineering test reactor (HTTR), which is the first HTGR in Japan, was successfully constructed at the Oarai Research Establishment of the Japan Atomic Energy Research Institute.

The HTTR achieved full power of 30 MW at a reactor outlet coolant temperature of about 850 • C on 7 December 2001 during the 'rise-to-power tests'. Two kinds of tests were carried out during the 'rise-to-power tests'. One is commissioning test to get operation permit by the government and another is test to confirm a performance of the reactor, heat exchanger, and control system.

From the test results of the 'rise-to-power tests' up to 30 MW, the functionality of the reactor and the cooling system were confirmed, and it was also confirmed that an operation of reactor facility could be performed safely.