The Role of Nitrogen in the Structure and Properties of Proton Irradiated 12Cr1MoWV Ferritic/Martensitic Steel for Advanced Nuclear Reactor Cores
The 12Cr1MoWV (wt%) ferritic/martensitic steel HT9 is a candidate material for fuel cladding in advanced nuclear reactors, such as the Versatile Test Reactor, currently under development. As such, understanding the relationship between microstructure and mechanical properties in the context of irradiation environments for these steels is critical. Nitrogen content has been hypothesized to have a significant effect on the irradiated properties of alloy HT9. In this work, three otherwise similar alloys of HT9 with varying N contents (10 ppm, 190 ppm, 440 ppm N) are thoroughly characterized prior ...
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