Safety aspects of intermediate heat transport and decay heat removal systems of sodium-cooled fast reactors
Copyright policy )Safety aspects of intermediate heat transport and decay heat removal systems of sodium-cooled fast reactors
AbstractTwenty 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.
Safety criteria, Nuclear Energy and Engineering, TK9001-9401, Nuclear engineering. Atomic power, Intermediate sodium system, Materials, Decay heat removal system, In-service inspection, Sodium-cooled fast reactor, Sodium-heated steam generator
Safety criteria, Nuclear Energy and Engineering, TK9001-9401, Nuclear engineering. Atomic power, Intermediate sodium system, Materials, Decay heat removal system, In-service inspection, Sodium-cooled fast reactor, Sodium-heated steam generator
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