Revaporisation of fission product deposits in the primary circuit and its impact on accident source term

The combination of the three different research approaches will enable a much improved understanding of major chemical interactions in the primary circuit and so permit a more accurate simulation of a severe accident in primary circuits of water-cooled reactors with the ASTEC integral code, using improved thermodynamic data in the SOPHEAROS module. This, in turn will help to reduce the uncertainties in the anticipated source term to the environment.