Size Effects in Deformation and Fracture of a Ferritic Reactor Pressure Vessel Steel
In support of small scale tests of reactor structures and to improve and extend basic knowledge, screening material tests of different families of geometrically similar specimens have been performed to examine the influence of size on the mechanical response. Homogeneous and especially non-homogeneous states of strain at different temperatures and strain rates were considered, among other nuclear steels, for the ferritic reactor pressure vessel steel 20MnMoNi55. For this material the main results of quasi-static tensile tests of smooth and notched specimens at room and elevated temperature, as well as the results of quasi-static three-point bending tests of notched beam specimens at room temperature and creep tests of smooth specimens at high temperatures are presented and discussed.
Bibliographic Reference: An oral report given at: 16th International Conference on Structural Mechanics in Reactor Technology SMiRT16. Organised by: Prof. Ajaya Kumar Gupta, North Carolina State University (US). Held in: Washington DC USA, 12-17 August, 2001
Record Number: 200013412 / Last updated on: 2001-06-27
Original language: en
Available languages: en