Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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CONCEPTUAL DESIGN OF THE SODIUM-COOLED FAST REACTOR KALIMER-600

  • Hahn, Do-Hee (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Kim, Yeong-Il (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Lee, Chan-Bock (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Kim, Seong-O (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Lee, Jae-Han (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Lee, Yong-Bum (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Kim, Byung-Ho (Fast Reactor Development Group, Korea Atomic Energy Research Institute) ;
  • Jeong, Hae-Yong (Fast Reactor Development Group, Korea Atomic Energy Research Institute)
  • Published : 2007.06.30
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Abstract

The Korea Atomic Energy Research Institute has developed an advanced fast reactor concept, KALIMER-600, which satisfies the Generation IV reactor design goals of sustainability, economics, safety, and proliferation resistance. The concept enables an efficient utilization of uranium resources and a reduction of the radioactive waste. The core design has been developed with a strong emphasis on proliferation resistance by adopting a single enrichment fuel without blanket assemblies. In addition, a passive residual heat removal system, shortened intermediate heat-transport system piping and seismic isolation have been realized in the reactor system design as enhancements to its safety and economics. The inherent safety characteristics of the KALIMER-600 design have been confirmed by a safety analysis of its bounding events. Research on important thermal-hydraulic phenomena and sensing technologies were performed to support the design study. The integrity of the reactor head against creep fatigue was confirmed using a CFD method, and a model for density-wave instability in a helical-coiled steam generator was developed. Gas entrainment on an agitating pool surface was investigated and an experimental correlation on a critical entrainment condition was obtained. An experimental study on sodium-water reactions was also performed to validate the developed SELPSTA code, which predicts the data accurately. An acoustic leak detection method utilizing a neural network and signal processing units were developed and applied successfully for the detection of a signal up to a noise level of -20 dB. Waveguide sensor visualization technology is being developed to inspect the reactor internals and fuel subassemblies. These research and developmental efforts contribute significantly to enhance the safety, economics, and efficiency of the KALIMER-600 design concept.

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References

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