Author(s)

P. Novosad

Abstract

Paper describes comparison of the static fracture toughness, dynamic fracture toughness and notch toughness of the nuclear reactor pressure vessels materials by testing the properties dependence on test temperature. Summarized are results of study of copper and phosphorus influence on radiation induced changes of Cr-Ni-Mo-V steel mechanical properties and influence of annealing on Cr-Mo-V steel. 1 Introduction The effects of neutron irradiation upon the properties of reactor pressure vessel materials is an important factor which may, among others, limit the plant life. In power reactor surveillance programes, based on tensile and Charpy-V type specimens, the limit plant life used to be derived from the drop of the upper shelf energy of Charpy specimens and the shift of their transition temperature under influence of neutro

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