Stability Estimation of ABWR on the Basis of Noise Analysis
スポンサーリンク
概要
- 論文の詳細を見る
In order to investigate the stability of a nuclear reactor core with an oxide mixture of uranium and plutonium (MOX) fuel installed, channel stability and regional stability tests were conducted with the SIRIUS-F facility. The SIRIUS-F facility was designed and constructed to provide a highly accurate simulation of thermal-hydraulic (channel) instabilities and coupled thermalhydraulics-neutronics instabilities of the Advanced Boiling Water Reactors (ABWRs). A real-time simulation was performed by modal point kinetics of reactor neutronics and fuel-rod thermal conduction on the basis of a measured void fraction in a reactor core section of the facility.A time series analysis was performed to calculate decay ratio and resonance frequency from a dominant pole of a transfer function by applying auto regressive (AR) methods to the time-series of the core inlet flow rate. Experiments were conducted with the SIRIUS-F facility, which simulates ABWR with MOX fuel installed. The variations in the decay ratio and resonance frequency among the five common AR methods are within 0.03 and 0.01 Hz, respectively. In this system, the appropriate decay ratio and resonance frequency can be estimated on the basis of the Yule-Walker method with the model order of 30.
- 一般社団法人 日本機械学会の論文
著者
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Furuya Masahiro
Central Research Institute Of Electric Power Industry
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MIZOKAMI Shinya
Tokyo Electric Power Company
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FUKAHORI Takanori
Global Nuclear Fuel-Japan Co., Ltd. (GNF-J)
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YOKOYA Jun
Electric Power Development Co., Ltd (J-POWER)
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MIZOKAMI Shinya
Tokyo Electric Power Co., Inc (TEPCO)
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