The objective of this paper is to analyze the ability a VVER-1000 core and its control system cope with hypothetical main steam line break (MSLB) accident in case multiple equipment failures. study involves use advanced 3D calculation models benchmarked validated for reactivity accidents preceding studies. A MSLB boundary condition problem solved on coarse (nodal) mesh coupled COBAYA/CTF neutro...

An open issue still under investigation by several international entities working on the safety and security field for the foreseen nuclear fusion reactors is the estimation of source terms that are a hazard for the operators and public, and for the machine itself in terms of efficiency and integrity in case of severe accident scenarios. Source term estimation is a crucial key safety issue to b...

The Low Energy Neutron Source (LENS) is an accelerator-based pulsed cold neutron facility under construction at the Indiana University Cyclotron Facility (IUCF). The idea behind LENS is to produce pulsed cold neutron beams starting with ∼MeV neutrons from (p,n) reactions in Be which are moderated to meV energies and extracted from a small solid angle for use in neutron instruments which can ope...

Framework • A detailed and highly flexible numerical tool to study criticality accidents has been developed The implements a Multi-Physics coupling using neutronics, thermal-hydraulics thermal-mechanics models based on Open FOAM SERPENT codes Two neutronics models: Quasi-Static Monte Carlo SPN Objective: In this work system composed by 2D square liquid fuel cavity filled with molten salt used t...

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...

The paper presents the results of a comparative analysis criticality calculations using Monte-Carlo code with BNAB-93 and BNAB-RF neutron group constants, as well evaluated data files from Russian ROSFOND nuclear library other libraries (ENDF, JEFF, JENDL) different years. A set integral experiments on BFS critical assemblies carried out in years at Institute Physics Power Engineering (60 confi...