While the conventional design of thermal power plants is mainly focused on high process
efficiency, market requirements increasingly target operating flexibility due to the continuing …

The FAST group at the Paul Scherrer Institut has been developing a code system for reactor
analysis for many years. For transient analysis, this code system is currently based on a …

Abstract The Laboratory for Reactor Physics and Systems Behaviour at the PSI and the
EPFL has been developing in recent years a new code system for reactor analysis based on …

Liquid metal cooled fast reactors are promising options for achieving the high degrees of
safety and sustainability demanded by the Generation IV paradigm. Among the critical …

Boiling can lead to unexpected heat transfer performance of the components using alkali
liquid metal (ALM) as working fluid for high thermal conductivity. Thus study on incipient …

The main objective of the presented work is to investigate the effectiveness of
homogenization of the GFR-2400 core in simulating its neutronic characteristics. To explore …

The reactor dynamics code DYN3D, initially developed for LWR applications, is being
extended for steady-state and transient analyses of Sodium cooled Fast Reactor (SFR) …

This paper discusses system codes benchmarking activities on an ASTRID-like
heterogeneous fast core under a representative design basis accident condition: the …

A new multi-physics solver for nuclear reactor analysis, named GeN-Foam (Generalized
Nuclear Foam), has been developed by the FAST group at the Paul Scherrer Institut. It is …

In the framework of cooperation agreements between KIT-INR and AREVA SAS NP as well
as between KIT-INR and EDF R&D in the years 2008–2013, the evaluation of severe …