Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure

By F. Garner, M. Toloczko, B. H. Sencer. 2000

507 citations recorded by the source corpus.

Subfields: Materials Chemistry, Mechanical Engineering

View Paper: https://www.semanticscholar.org/paper/e046a182da6ed0faae6bebeb1f7bc047fafa4a90

Citations in the corpus

• Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications (2017, unknown): “2%/dpa post-transient steady state swelling rate for fission neutron irradiated ferritic martensitic steels [104] is also shown in the figure.”