Approaches towards an advanced pressurized water reactor (APWR)

The investigations made up to now indicate the ''key problems'' to be expected in developing the Advanced Pressurized Water Reactor (APWR): Verification of a sufficient negative void reactivity, description of the cladding (zircaloy or steel) deformation performance at LOCAs, assurance of heat removal during and especially offer accidental sequences (refloodability of the densely packed core), assessment of the fuel performance at high burn-up (50 to 60 MWd/kg f.m.), and influence of the increased enrichment in fissionable material on general problems of safety. The solution of these problems requires - apart from theoretical efforts - a considerable experimental program to support the results. (orig./RW)