OS8-6 高温ガス炉の炉特性・安全性解析手法の開発・検証(OS8 軽水炉・新型炉・核燃料サイクル,分散と集中の共存)

概要

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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 used a conventional method, which uses a one-dimensional flow channel model and a reactor kinetics model with a single temperature coefficient taking into account the temperature variation of the core. However, it was found that there is a slight difference between the analytical results and the experimental ones ; therefore, we have modified this code to use a model with four parallel flow channels and twenty temperature coefficients in the core. This paper describes the validation results of the newly developed code using the experimental results. 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
2006-06-28