Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project


	Typical axial sweep of the radial temperature distribution on the surface of the central fuel rod simulator behind the spacer grid. Rose’s alloy: T= 150 oC, Re = 8000.

Part of: Bolshov LA, Strizhov VF, Mosunova NA (2020) Codes of new generation for safety justification of power units with a closed nuclear fuel cycle developed for the “PRORYV” project. Nuclear Energy and Technology 6(3): 203-214. https://doi.org/10.3897/nucet.6.54710