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Performance test of HTTR

HTTRの出力上昇試験

中川 繁昭; 橘 幸男; 高松 邦吉; 植田 祥平; 塙 悟史

Nakagawa, Shigeaki; Tachibana, Yukio; Takamatsu, Kuniyoshi; Ueta, Shohei; Hanawa, Satoshi

高温ガス炉は冷却材温度を高温にすることができるとともに、固有の安全性があることで魅力的な原子炉である。日本初の高温ガス炉であるHTTRが日本原子力研究所の大洗研究所に建設された。HTTRは、その出力上昇試験において2001年12月7日に原子炉出力30MW,原子炉出口冷却材温度850$$^{circ}$$Cを達成した。出力上昇試験では、運転合格証取得のための試験と原子炉性能確認のための試験の2種類を実施した。原子炉出力30MWまでの出力上昇試験の結果から、原子炉及び冷却機器の性能を確認し、原子炉施設の運転が安全に実施できることを確認した。本論文は、HTTRに関するシリーズ投稿の一つである。

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 30MW at a reactor outlet coolant temperature of about 850$$^{circ}$$C on December 7, 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, control system. From the test results of the "rise-to-power tests" up to 30MW, the functionality of the reactor and the cooling system were confirmed, and it was also confirmed that an operation of reactor facility can be performed safely.

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パーセンタイル:59.89

分野:Nuclear Science & Technology

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