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Present status of HTTR and its test experience

HTTRの現状と試験経験

伊与久 達夫; 野尻 直喜 ; 藤本 望; 篠原 正憲 ; 太田 幸丸; 橘 幸男 

Iyoku, Tatsuo; Nojiri, Naoki; Fujimoto, Nozomu; Shinohara, Masanori; Ota, Yukimaru; Tachibana, Yukio

高温ガス炉は発電のみならず水素製造などに利用できることから、世界的に注目されている。原子力機構は、我が国初の高温ガス炉であるHTTR(高温工学試験研究炉)を大洗サイトに建設した。HTTRは2004年4月19日に原子炉出口冷却材温度950$$^{circ}$$Cを達成した。これは原子炉圧力容器外に取り出した冷却材温度として世界最高である。HTTRにおいては、出力上昇試験,長期間の高温連続運転試験,高温ガス炉固有の安全性を確認するための安全性実証試験等を計画し、実施してきている。本報は、今までHTTRで実施した試験の内容を述べるとともに、今後計画している試験内容を紹介する。

The High Temperature Gas-cooled Reactor (HTGR) is expected to be one of the most promising energy sources not only for electricity generation and but also for process heat applications such as hydrogen production, desalination, etc. In Japan, since 1960s Japan Atomic Energy Agency (JAEA) has been developing HTGR technologies such fuel, high temperature metal, graphite, core physics, thermal hydraulics control and so forth. These technologies were well developed and used to design and construct the Japan's first HTGR, High Temperature Engineering Test Reactor (HTTR). It is a graphite-moderated and helium-cooled HTGR with the rated thermal power of 30 MW and the maximum outlet coolant temperature of 950$$^{circ}$$C. The HTTR achieved the reactor outlet coolant temperature of 950$$^{circ}$$C on April 19, 2004. It is the highest coolant temperature outside reactor pressure vessel in the world. So far, basic performance data of the HTTR during the power-up and long-term high temperature operation tests are accumulated. Except that, various unique tests concerning the HTGR safety are conducted to confirm inherent safety characteristics of the HTGR.

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