Разработка программного обеспечения для оценки активности и нуклидного состава ТВС типа ИРТ-3М во время хранения

Abstract

Analytical dependencies were obtained for spent fuel assembly. Using these dependencies allow calculate nuclide composition depending on the burnout and the activity of fuel assembly depending on the storage time. Using the obtained results mathematical model was developed, and based on the model program was developed. This program calculates the activity of FA at any time considering time and mode of operation. The resulting computational model showed high agreement with the experimental data, and this, in turn, allows for further research activity of the irradiated fuel assembly at the stage of storage and recycling.