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高温ガス炉における制御棒引抜き試験解析の高度化

Improvement of core dynamics analysis of control rod withdrawal test in HTGR

高松 邦吉; 中川 繁昭

Takamatsu, Kuniyoshi; Nakagawa, Shigeaki

高温工学試験研究炉(High Temperature engineering Test Reactor: HTTR)は原子炉出力30MW,原子炉出口冷却材温度(定格運転850$$^{circ}$$C/高温試験運転950$$^{circ}$$C)の黒鉛減速ヘリウムガス冷却型の高温ガス炉である。高温ガス炉の固有の安全性を定量的に実証するため、HTTRでは反応度投入事象として制御棒引抜き試験を実施している。従来の解析モデルを用いた1点炉近似による動特性解析では、制御棒引抜き事象を十分再現できないことが明らかになっている。本研究において、新たに領域別温度係数を用いて解析を行った結果、試験時の実測値を正確に再現することができ、高温ガス炉の動特性解析手法を高度化することができた。

The HTTR (High Temperature Engineering Test Reactor), which has thermal output of 30MW, coolant inlet temperature of 395$$^{circ}$$C and coolant outlet temperature of 850$$^{circ}$$C/950$$^{circ}$$C, is a first high temperature gas-cooled reactor (HTGR) in Japan. The HTGR has a high inherent safety potential to accident condition. Safety demonstration tests using the HTTR are underway in order to demonstrate such excellent inherent safety features of the HTGR. A one-point core dynamics approximation with one fuel channel model had applied to this analysis. It was found that the analytical model for core dynamics couldn't simulate the reactor power behavior accurately. This report proposes an original method using temperature coefficients of some regions in the core. It is crucial to evaluate this method precisely to simulate a performance of HTGR during the test.

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