Abstract The aim of the paper is to present results and insights gained from analysis postulated severe accident scenario for Nuclear Power Plant (NPP) equipped with a VVER-1000, focusing on uncertainty assessment in prediction selected Fission Products (FPs). To this end, simulation Large Break Loss Coolant Accident (LB LOCA) along Station Blackout (SBO) was carried out. capabilities ASTECv2.2...

In this paper, neutronic calculations and the core analysis of VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 ENDF/B-VIII libraries. The effect thorium introduction on parameters was discussed. reference initially filled enriched uranium oxide fuel then fueled uranium-thorium fuel. determine delayed neutron fraction βeff, temperature reactivity coefficients, c...

Novel codes allow the prediction of parameters with increased resolution, in comparison to conventional approach, sometimes using meshing smaller than size fuel pin. Optimally, complex geometric structures, like ones included VVER core e.g. corner stiffeners, would be modeled explicitly by novel neutronic codes. In this paper, performance deterministic neutron transport code nTF is studied for ...

The first stage of a core degradation—based on the defense-in-depth concept nuclear power plant (NPP) safety—is prone to fuel melting due local blockage. flow blockage accidents with no SCRAM happening can lead fuel-clad failure, consequently affecting safety NPP. present study provides an analysis Anticipated Transient Without (ATWS), which might condition burning out. related ATWS scenarios, ...