This report covers the current capabilities of the available codes that will be used within the R2CA H2020 project in the release evaluation methodologies of LOCA and SGTR transients in different kinds of reactors (PWRs, VVERs, EPR, BWR) displaying both code descriptions and model comparison tables. It includes both system codes and codes focusing on a part of the phenomenology only, in particular focusing on the determination of the fuel rod failures as well as on the consequences of these failures. A state of the art of the combined use of these codes in implementation of the release evaluation methodologies is also described. The work that has been done covers fuel performance, sub-channel and system thermal-hydraulics, radionuclide transport and integral system behaviour. Codes modelling only the steady-state operation (especially fuel codes) have also been included as they produce initial conditions for the transient codes and are integral part of the calculation chains. Finally, the developments items for the codes, that will be addressed within the R2CA project, are also summarized dealing with cladding modelling, fuel and fission product modelling, code coupling and whole core modelling and nodalization.