Abstract
The paper presents analysis of thermal condition of a fuel assembly (FA) with low-enriched uranium (LEU) fuel of the IVG.1M reactor at design accidents due to failure of control and protection system (CPS). The accidents with spontaneous turning of one control dram as well as dram control system with peak efficiency were considered. The issue of research presented in the article was in conduction of nonsteady heat computation of reactor’s FA with double profiling of energy release throughout the height of the assembly and in time. Based on results of the computation research, charts of changes of temperature peak values of FAs and water at the outlet from water-cooled technological channel at design accidents with ejection of CPS actuating device were obtained.