[en] The project of a power unit with BN-1200 reactor is designed using advanced technical solutions, which define evolution of the fast breeder technology in the field of safety parameters and in the field of technical and economical indicators. At present there was completed estimation of the BN-1200 project from the point of view of its compliance with the requirements of nuclear energy systems of Generation IV in the frames of International forum Generation IV, and comparison of the BN-1200 project with other fast breeder projects using NESA INPRO procedure, developed and verified for comparison of nuclear energy systems with PWR. The paper presents the results of preliminary estimation by the INPRO procedure, which showed that BN-1200 has good margin of safety and economical characteristics in comparison with the previous projects; and BN-1200 meets all the basic principles in the fields of ‘safety’ and ‘economics’; and BN-1200 can ensure sustainable development of the nuclear energy system. Estimation results of the BN-1200 concept for compliance with the requirements to Generation IV plants testify that BN-1200 project, as a whole, has good potential from the point of view of compliance with the stated requirements. (author)

[en] The paper considers the BN-1200 fuel cladding tightness monitoring systems and other available fuel cladding tightness monitoring systems of fast reactors and discusses possibilities to apply their development and operation experience for development of the BN-12000 fuel cladding tightness monitoring system. (author)

[en] The main feature of the next stage of SFR development is simultaneous achievement of the goals of improvement of economical and safety characteristics. In our vision the main path for this is max use of inherent safety characteristics, as well as safety systems based on passive operating principles. This approach was used in optimization of characteristics of BN-1200 in the stage of its conceptual design. The main characteristics of the BN-1200 reactor taken for design development are presented.

[en] The design of the BN-1200 sodium-cooled fast reactor is analyzed from the standpoint of its compliance with the criteria fitting the promising Gen-IV reactor facilities. The basic technical solutions adopted in the BN-1200 design making it possible to meet the requirements of consistent development of non-proliferation and safety, cost-effectiveness, and physical protection are described. The BN-1200 concept is evaluated on the basis of 26 criteria developed as part of the Generation IV international forum for the Gen-IV sodium-cooled fast reactor. The compliance of the safety requirements used in the development of the BN-1200 design with the design criteria for the Gen-IV sodium-cooled fast reactor developed as part of the Generation IV international forum is analyzed.

[en] The power unit with the BN-1200 reactor plant was analyzed considering requirements imposed to innovative nuclear technologies, including IAEA recommendations. The BN-1200 design considers the following types of beyond-design accidents: - heat-removal accidents with loss of power, failures of active systems of reactor shutdown, failures of normal cooldown systems and active elements of emergency cooldown; - accidents with positive reactivity introduction and failures of active reactor shutdown systems; - accidents with blockage of fuel assembly flow area. Design safety analysis for beyond-design accidents was made by verified codes, developed under the Federal Target Program. A complex approach, which analyzes main processes and phenomena taking place in the reactor plant and power unit rooms during accident, is used for safety assurance. The analysis results show that evacuation of population is not required for the expected exposure doses outside the nuclear power plant. (author)

No abstract available

[en] The project of a power unit with BN-1200 reactor is designed using advanced technical solutions, which define evolution of the fast breeder technology in the field of safety parameters and in the field of technical and economical indicators. At present there was completed estimation of the BN-1200 project from the point of view of its compliance with the requirements of nuclear energy systems of Generation IV in the frames of International forum Generation IV, and comparison of the BN-1200 project with other fast breeder projects using NESA INPRO procedure, developed and verified for comparison of nuclear energy systems with PWR. The paper presents the results of preliminary estimation by the INPRO procedure, which showed that BN-1200 has good margin of safety and economical characteristics in comparison with the previous projects; and BN-1200 meets all the basic principles in the fields of ‘safety’ and ‘economics’; and BN-1200 can ensure sustainable development of the nuclear energy system. Estimation results of the BN-1200 concept for compliance with the requirements to Generation IV plants testify that BN-1200 project, as a whole, has good potential from the point of view of compliance with the stated requirements. (author)

[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] An example of a limited scope INPRO sustainability assessment of an innovative nuclear energy system used the BN-1200 fast reactor as a case study. The INPRO assessment was performed at the full-depth criteria level and helped to identify actions for sustainable long term deployment of sodium cooled fast reactors. The publication describes the application of the INPRO sustainability assessment method to the innovative nuclear energy system based on BN-1200 fast reactors in the areas of economics and safety of nuclear reactors. The case study is intended to verify readiness of the updated INPRO Methodology for assessment of the sodium cooled fast reactors and to develop recommendations for further improvements to the INPRO assessment method.

No abstract available