Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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SAFETY ASPECTS OF INTERMEDIATE HEAT TRANSPORT AND DECAY HEAT REMOVAL SYSTEMS OF SODIUM-COOLED FAST REACTORS

  • Received : 2014.12.15
  • Accepted : 2015.01.07
  • Published : 2015.04.25
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Abstract

Twenty sodium-cooled fast reactors (SFRs) have provided valuable experience in design, licensing, and operation. This paper summarizes the important safety criteria and safety guidelines of intermediate sodium systems, steam generators, decay heat removal systems and associated construction materials and in-service inspection. The safety criteria and guidelines provide a sufficient framework for design and licensing, in particular by new entrants in SFRs.

Keywords

References

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