[en] Conclusion: Comparison of safety requirements used in development of the BN-1200 design with safety design criteria for the Generation-IV SFR developed by the SDC TF demonstrates their compliance. This leads to the conclusion that the BN-1200 design meets the safety design criteria for the Generation-IV SFR

[en] BN-1200 design should meet the following safety requirements: • Current regulatory safety requirements for operating nuclear power plants; • Core damage frequency should not exceed 10^-6 1/reactor·year; • Large early release frequency should not exceed 10^-7 1/reactor·year; • Elimination of accidents with consequences requiring the need for offsite public evacuation. In any technically credible situation, the following requirements must be implemented: • Removal of decay heat generated by the reactor while maintaining its structural integrity; • Localization of the majority of radioactive products escaping from the reactor in the event of potential accidents within a special above-reactor premise; • The reactor should go subcritical while maintaining acceptable temperature conditions of its components. Implementation of all of these requirements should ensure achievement of the objective of precluding offsite public evacuation

[en] Conclusions: • BN-1200 reactor design provides Safety Design Criteria for Generation-IV Sodium-cooled Fast Reactor System implementation; • Sodium-cooled fast reactors design and operating experience accumulated in Russia confirms technology maturity and ability for developing BN-1200 as sodium-cooled fast reactor design for serial construction; • BN-1200 reactor design safety provisions due to optimal combination of proven and new solutions allow to consider this design as design of Generation IV systems