, Conceptual design studies, phase 1 /2 of ASTRID project A800: Alloy 800 austenitic steel BN600: 600 MWe SFR in Russia DEGF: Double Ended Guillotine Failure DNB: Departure of Nucleate Boiling IHX: Intermediate Heat eXchanger ISI&R: In-Service Inspection & Repair JAEA: Japan Atomic Energy Agency PFR: Prototype Fast reactor (UK) PFBR: Prototype Fast Breeder Reactor (India) RCC-MR: French code for Design and Manufacturing of SFR components and structures R&D, ASTRID: Advanced Sodium Technological Reactor for Industrial Demonstration AVP1 Research and Development SFR: Sodium Fast Reactor SG: Steam Generator SPX: Superphenix
, SWR: Sodium Water Reaction SWAR: Sodium Water Air Reaction TNa: Sodium Temperature TRL: Technology Readiness Level Twater: Water Temperature T91: Grade 91martensitic-ferritic steel 1D: One-Dimensional REFERENCES
Safety improvement research to design a sodium fast reactor steam generator with regard to sodium/water reaction risk, Proceedings of ICAPP'10, Paper 10067, 2010. ,
Sodium-Water Reaction approach and mastering for ASTRID Steam Generator design, In: Int. Conf. on Fast React. and Related Fuel Cycles: Safe Technol. and Sustainable Scenarios, pp.13-17, 2013. ,
Cooperation on impingement wastage experiment of Mod 9Cr?1Mo steel using SWAT-1R sodium?water reaction test facility, In: Int. Conf. on Fast React. and Related Fuel Cycles: Safe Technol. and Sustainable Scenarios, pp.13-17, 2013. ,
Thermomechanical model and bursting tests to evaluate the risk of swelling and bursting of Mo. 9Cr-1Mo steel Steam Generator tubes during a Sodium-Water Reaction incident Article ID 974581, 5. O. M. Saraev, Operating experience and development of sodium-cooled fast reactor, Science and Technology of Nuclear Installations Atomic Energy, vol.2013, issue.108 4, 2010. ,
Computer Program for the Finite Element Simulation of Fluid-Structure Systems under Transient Dynamic Loading ,