Quantification of brittle-ductile failure behavior of ferritic reactor pressure vessel steels using the Small-Punch-Test and micromechanical damage models

摘要: Abstract Two German ferritic pressure vessel steels are examined in the brittle to ductile transition regime as a function of temperature and irradiation. The experiments done by miniaturized Small-Punch-Test hot cells within range −185 °C up 70 °C. From load–displacement curve SPT, yield curves parameters both non-local G urson -T vergaard -N eedleman damage model modified B eremin identified. influence irradiation on is analyzed. All verified comparison with results from standard test methods. parameters, identified used simulate failure behavior fracture mechanics specimens. In upper shelf, GTN-model applied crack resistance curves, where toughness data could be successfully predicted. lower W eibull -stress specimens was computed find out statistics values. Finally, were combined evaluate brittle-ductile region. This way, an acceptable agreement Master-curve for non-irradiated achieved whole range.