This paper describes the results of an analysis of loss of coolant accidents (LOCA's) for the Soviet designed, light water cooled and moderated reactors referred to as VVERs. The VVER unit selected for this analysis is designated as VvER-440 Model 213. This plant generates 440 Mwe and is of current interest since meen are now operating and additional units are in various stages of construction ...

This work deals with the assessment of burnup capabilities Serpent Monte Carlo code to predict spent nuclear fuel (SNF) isotopic concentrations for low-enriched uranium (LEU) at different levels up 47 MWd/kgU. The irradiation six UO2 experimental samples in three VVER-1000 reactor units has been simulated and predicted actinides 244Cm have compared corresponding measured values. results show a ...