Analysis of selected Phenix EOL tests with the FAST code system – Part II: Unprotected phase of the Natural Convection Test

GeN-Foam: a novel OpenFOAM® based multi-physics solver for 2D/3D transient analysis of nuclear reactors

“…However, a generally good agreement is observed. In fact, discrepancies of this magnitude can typically be expected between a point-kinetics and a spatial-kinetics model (Chenu et al, 2012).…”

“…Specifically, a coupled TRACE-PARCS routine has been adapted for fast reactor (FR) analysis and validated against relevant experimental data (Chenu et al, 2012). Following the trends discussed above, efforts are currently being directed toward stepping beyond explicit data exchange interfaces and use of legacy codes.…”

Analysis of unprotected transients with control and safety rod drive mechanism expansion feedback in a medium sized oxide fuelled fast breeder reactor

“…Other than the above said feedback, some more feedbacks are available to protect the reactor against any transients. They are the control rod drive line expansion feedback (Chenu et al, 2012), vessel expansion feedback and grid plate expansion feedback. Upon rise in outlet coolant temperature, there is an expansion of control rod drive line which passes through the annular space between drive mechanism and the protective shroud tube.…”