S0803-1-2 ナトリウム冷却高速炉の炉心出口近傍での温度変動に対する高サイクル熱疲労評価手法の検討(原子力発電システムおよび要素技術(1))

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タイトル別名
  • S0803-1-2 Investigation on High Cycle Thermal Fatigue Evaluation Method against Temperature Fluctuation near Core Outlet in Sodium Cooled Fast Reactor

抄録

Hot and cold fluids are mixed at the core outlet of sodium cooled fast reactors. The temperature fluctuation causes high cycle thermal fatigue in structural components. The temperature fluctuation at the core outlet region has not a sinusoidal waveform but an irregular spike waveform. In the study, the evaluation method for the high cycle thermal fatigue was investigated against the spike waveform of temperature fluctuation. It was found that the combinational method between the peak-to-peak value of temperature fluctuation and the frequency response function of structure could evaluate the fatigue damage in structure.

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