(1)
Mondal, J.; Afsar, S. M. A. . Analysis of Nuclear Reactor Parameters in the VVER-1200 During a Loss of Coolant Accident and Steam Generator Tube Rupture With Emergency Core Cooling System Failure. SCS:Engineering 2025, 3, 1-6. https://doi.org/10.38032/scse.2025.3.3.