作者: A. Legris , B. Rouxel , P. Gavoille , C. Cabet , A. Vaugoude
DOI:
关键词:
摘要: Due to their good corrosion resistance and excellent creep properties between 400C 700C, austenitic steels have been chosen as reference material for the cladding materials French Sodium Fast Reactor (SFR) program. However, due swelling phenomenon under irradiation, lifespan is limited new advanced are developed increase radiation tolerance GEN IV reactors.Currently in France, most optimized steel AIM1, a 15Cr-15Ni stabilized with titanium. A generic study conducted around this understand mechanisms will benefit future AIM2 design, an improved variation of AIM1. Swelling behaviour depends on various microstructural such dislocation density, shape nature precipitates elements solid solution. Their role voids formation growth complex. The objective appreciate these metallurgical parameters mechanisms. Model different content Ti Nb, compared produced. In order swelling, states generated thermomechanical treatment. To simulate neutron selected samples were irradiated at 600C up 120dpa 2MeV Fe2+ JANNuS facility CEA Saclay (France). resulting microstructures analysed by Transmission Electron Microscopy effects void highlighted. particular, solution density main which influence irradiation conditions. Replacing titanium niobium, behavior significantly different. Niobium seems be inhibitor coupled niobium discussed.