The present work is part of a larger multi-scale effort aiming to increase knowledge of thephysical phenomena underneath reactor pressure vessel irradiation embrittlement. Withinthis framework, we focused on the description of dislocation mobility in BCC iron, which is oneof the key inputs to dislocation dynamics (DD) simulation codes. An extensive bibliographicreview shows that none of the available expressions can deal with the ductile-fragile transitiondomain of interest. Here, a new screw mobility law able to reproduce the main experimentalobservations is introduced building on the previous models. The aforementioned law is usedtogether with an improved dislocations dynamics code Tridis BCC 2.0, featuring bothperformance and dislocations segments interaction management enhancements, that allowsfor complex DD simulations of BCC iron structures with cross-slip
