OS8-10 高温ガス炉の炉特性・安全性解析手法の高度化 : 冷却材流量喪失試験(OS8 軽水炉・新型炉・核燃料サイクル,循環型社会における動力エネルギー技術)

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The high temperature engineering test reactor (HTTR) is a graphite-moderated gas-cooled reactor with a thermal power of 30MW and a reactor outlet coolant temperature of 950℃. Safety demonstration tests using the HTTR are in progress to verify the inherent safety features and to improve the safety technology and design methodology of high temperature gas-cooled reactors (HTGRs). The numerical analysis code was developed to analyze the reactor dynamics including the flow behavior in the HTTR core. We have modified this code to use a model with four parallel flow channels and twenty temperature coefficients in the core. This paper describes an analytical result of the loss of partial coolant flow test using the newly developed code. The analytical result of transient reactor power shows good agreement with the measured value during the test. Moreover, this paper refers to an analytical result of the loss of coolant flow test. The reactor power decreases to decay heat level due to the negative reactivity feedback effect of the core. Although the reactor power becomes critical again later, the peak power value is very small. It was confirmed that the developed code could not only analyze the reactor core dynamics but also simulate the core dynamics during the abnormal events postulated in the HTGR safety analysis. This code can also be applied for the safety analysis of the very high temperature reactor (VHTR), which is one of the Generation IV reactor concepts.
一般社団法人日本機械学会の論文
2007-06-13

OS8-10 高温ガス炉の炉特性・安全性解析手法の高度化 : 冷却材流量喪失試験(OS8 軽水炉・新型炉・核燃料サイクル,循環型社会における動力エネルギー技術)

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