Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Influence of design modification of control rod assembly for Prototype Generation IV Sodium-cooled Fast Reactor on drop performance

  • Son, Jin Gwan (Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute) ;
  • Lee, Jae Han (Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute) ;
  • Kim, Hoe Woong (Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute) ;
  • Kim, Sung Kyun (Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute) ;
  • Kim, Jong Bum (Sodium-cooled Fast Reactor NSSS Design Division, Korea Atomic Energy Research Institute)
  • Received : 2018.08.17
  • Accepted : 2018.11.25
  • Published : 2019.04.25
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Abstract

This paper presents the drop performance test of the control rod assembly which is one of the main components strongly related to the safety of the prototype generation IV sodium-cooled fast reactor. To investigate the drop performance, a real-sized control rod assembly that was recently modified based on the drop analysis results was newly fabricated, and several free drop tests under different flow rate conditions were carried out. Then the results were compared with those obtained from the previous tests conducted on the conceptually designed control rod assembly to demonstrate the improvement in performance. Moreover, the drop performance tests under several types and magnitudes of seismic loadings were also conducted to investigate the effect of the seismic loading on the drop performance of the modified control rod assembly. The results showed that the effects of the type and magnitude of the seismic loading on the drop performance of the modified control rod assembly were not significant. Also, the drop time requirement was successfully satisfied, even under the seismic loading conditions.

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References

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