The LVR-15 research reactor is operated with a tube type fuel IRT-4M. Due to fuel’s unique concentric square annular shape with, coolant flow subject significant pressure driven crossflow. Detailed calculation of such patterns beyond capabilities standard system codes used for the thermal hydraulic safety analysis. To assess core designs consisting IRT-4M assemblies, new subchannel code under d...

Temperature Classifications..................................................... 12.1 CLOSED WATER SYSTEMS.................................................... 12.2 Method of Design ..................................................................... 12.2 Thermal Components ............................................................... 12.2 Hydraulic Components ...................................

The safety assessment of Nuclear Power Plants makes use of Thermal-Hydraulic codes for the quantification of the safety margins with respect to upper/lower safety thresholds, when postulated accidental scenarios occur. To explicitly treat uncertainties in the safety margins estimates within the Risk-Informed Safety Margin Characterization (RISMC) framework, we resort to the concept of Dynamic P...

Probabilistic Safety Assessment (PSA) is a mathematical tool to evaluate numerical estimates of risk for nuclear power plants (NPPs). For the last couple of years, PSA has been put to practical use for verification of safety in research and industrial fields. However, PSA still has the problems about the quality and reliability. The significant one of the problems is that the quantification of ...