Professor and Director, Staatliche Materialprüfungsanstalt, University of Stuttgart, Stuttgart,
Pages: 13 Published: Jan 1983
Reactor pressure vessels of nuclear installations are subjected to operating parameters that lead to a change in material and flaw state. The safety margin of both the material for older vessels and the optimized material has to be quantified with reference to extremely long-term effects. Research programs in West Germany are focused on assessing criteria for the applicability of small-scale specimen testing to component behavior under all realistic and postulated loading conditions. The problem will be treated theoretically and experimentally for a wide range of materials, including the worst-case material state at the end of life.
light water reactors, pressure vessel steels, irradiation, fracture mechanics, pressurized thermal shock, large scale specimens, intermediate size vessels, welded joints
Paper ID: STP31845S