The critical heat flux (CHF) is an important thermal-hydraulic parameter that must be determined during the design of water-cooled reactors to ensure safety operation. In this paper, a methodology proposed predict CHF in VVER rod bundles. A whole-reactor model VVER-1000 implemented RELAP-SCDAPSIM, and, based on bundle-average approach, parameters hot channel are used assess four predictors (i.e...

This article is focused on the current issue of developing an operator information support system (OISS) for Novovoronezh NPP II project. One main reasons to raise this topic MCR operator’s overload with data due greatly increased flows related VVER-1200 Process I&C compared serially produced VVER-1000 power units. The other important reason, in authors’ opinion, volume existing procedu...

The two-phase emission detector RED-100 with 130 kg of liquid xenon as a working medium has been exhibited at distance 19 m from the core VVER-1000/320 nuclear power reactor fourth unit Kalinin Nuclear Plant Power in 2021–2022. Due to high sensitivity for weak ionization signals (down single electrons), used search elastic coherent scattering electron antineutrinos off nuclei. However, observat...

During the design of nuclear power plant with VVER-1000 units, which today form basis industry Ukraine, development information and computing systems (IСS) was insufficient to solve many tasks due small capacities systems. Currently, newer ones, capabilities are thousands times greater than their predecessors, have replaced IСS. IСS download currently does not exceed 1 %...2 %, this is use simp...