The safety performance of nuclear power plants (NPPs) is a very important factor in evaluating energy sustainability. Safety analysis passive and active systems have positive influence on reactor transient mitigation. One the common transients primary coolant leg rupture. This study focused guillotine large break loss (LB-LOCA) one vessels, which cold rupture occurred, after establishment stead...

The development and the validation of old new software in relevant DEMO reactor conditions have been exploited latest years within EUROfusion Consortium. aim was to use—if possible—the already validated for fission reactors fill gaps with ad-hoc software. As contribution this effort, Karlsruhe Institute Technology (KIT) developed tested a novel apply Best-Estimate Model Calibration Prediction t...

The paper presents the RELAP5/mod3.3 analysis of natural circulation cooldown with one inactive loop for Nuclear Power Plant Krško (NEK). aim is to determine limiting rates during operator recovery actions minimize effect flow stagnation in loop. Since this typical asymmetrical transient, NEK model split reactor vessel was developed (models and core were axially divided two parts) used analysis...

In order to explore the hydrogen source term characteristics under severe accidents of marine pressurized water reactors (PWR) and effectively assess risk, best estimation program SCDAP/RELAP5/MOD3.2 is used establish reactor accident analysis model. Based on Latin Hypercube sampling (LHS) method Wilks theory, a set methods for uncertainty developed. This can be applied sensitivity different ta...

This report has been prepared as a part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program. KS-i Test 35-1 data on the behaviour of the heated rod temperatures in the partially uncovered VVER Core model were simulated with RELAP5/MOD3.2 to assess the code, especially its non equilibrium (unequal phase temperatures) ...