Integrity Evaluation of Control Rod Assembly for Sodium-Cooled Fast Reactor due to Drop Impact

낙하충격에 의한 소듐냉각고속로 제어봉집합체의 건전성 평가

  • Received : 2016.07.24
  • Accepted : 2016.10.14
  • Published : 2017.03.01


The CA (Control Assembly) of an SFR has a CRA(Control Rod Assembly) with an inner duct and control rod. During an emergency situation, the CRA falls into the duct of the CA for a rapid shut-down. The drop time and impact velocity of the CRA are important parameters with respect to the reactivity insertion time and the structural integrity of the CRA. The objective of this study was to investigate the dynamic behavior and integrity of the CRA owing to a drop impact. The impact analysis of the CRA under normal/abnormal drop conditions was carried out using the commercial FEM code LS-DYNA. Results of the drop impact analysis demonstrated that the CRA maintained structural integrity, and could be safely inserted into the flow hole of the damper under abnormal conditions.


Sodium-cooled Fast Reactor;Control Assembly;Control Rod Assembly;Drop Impact;Integrity Evaluation


Supported by : National Research Foundation (NRF)


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