S.I. Pantyushin

1. Analysis of uncertainties for results of experiment with boiling-off the coolant simulation using SOCRAT-B1/B2-code for spent fuel pool conditions
   2023/03/22 by M.M. Bedretdinov, M. M. Bedretdinov, S.I. Pantyushin +4 · 1 citation
   Engineering · Materials Science · #Nuclear Engineering Thermal-Hydraulics #Nuclear reactor physics and engineering #Nuclear Materials and Properties
2. The new research program for loss of cooling conditions in spent fuel pools of VVER type reactors
   2026/07/25 by O.E. Stepanov, О. Е. Степанов, M. M. Bedretdinov +5
   Engineering · Materials Science · #Nuclear Engineering Thermal-Hydraulics #Nuclear Materials and Properties #Graphite, nuclear technology, radiation studies