Cerca nel sito per parola chiave

pubblicazioni - Presentazione

Analyses of Trace-Parcs Coupling capability by simulating a MSLB Transient

pubblicazioni - Presentazione

Analyses of Trace-Parcs Coupling capability by simulating a MSLB Transient

Per fornire una valutazione delle potenzialità dell’accoppiamento dei codici TRACE e PARCS nella simulazione di transitori in impianti nucleari caratterizzati da una forte interazione tra la termoidraulica e la neutronica, il lavoro presenta i risultati ottenuti attraverso il benchmark OECD/NEA PWR MSLB (rottura di una tubazione principale del vapore).

The best estimate thermal hydraulic and three-dimensional neutron kinetic codes give a valuable contribution in improving design, optimization and safety measures of nuclear reactor systems.In order to model the interaction between neutron kinetic and thermal hydraulic phenomena and their spatial distribution, taking place during steady and transient condition, in a more accurate way, advanced calculation techniques have been developed by coupling best estimate thermal hydraulic and three-dimensional neutron kinetic codes.

The resulting coupled calculated data give the possibility of developing more accurate studies and reduce the related calculation uncertainties. In order to analyze the best estimate capability of TRACE/PARCS coupled codes to simulate transients, characterized by a strong thermal hydraulic and neutronic interaction and test their thermal hydraulic/neutronic code coupling, the simulation of the benchmark problem OECD/NEA PWR MSLB (Main Steam Line Break) is reported and discussed.

Progetti

Commenti