Irradiation-resistant austenitic steels material

Irradiation-resistant austenitic steels as core materials for Generation IV nuclear reactors... 

The objective of this chapter is to present an update on the progress carried out on the knowledge of the irradiation-resistant austenitic steels used as core structural materials of Generation IV systems. In the following we will focus on the SFR core materials because it is in these reactors that irradiation-resistant austenitic steels are mostly used and because the experience feedback is the most important. 

It seems that, beyond the progresses realized from the first 300-series steels to the present reference materials (15-15Ti and D9 derivatives), it would be possible to find an ultimate upgrade in the family of irradiation-resistant austenitic steels using a CW 12-15/15-25 Ti + Nb stabilized and P-doped matrix, but further work has yet to be done to specify the content of other alloying elements (Mo, Mn, C, Si, N, B) and to adjust the fabrication route to optimize the in-pile behavior of such advanced austenitic material for high-dose applications. 

In this chapter devoted to the irradiation-resistant austenitic steels for core applications in the Generation IV reactors, we focus on the SFR core materials because this type of material has been almost exclusively used in this type of reactor which was the subject of many developments and thus, because it is of important international feedback. 

For austenitic steels, correlations between resistance to swelling and the stability of austenite were suggested as early as the 1970s to explain the large diversify in the behavior of this class of materials. Johnston [35] clearly demonstrated the beneficial effect of Ni between 15% and 60% and conversely the harmful effect of Cr between 7% and 30% on the resistance to swelling of ternary alloys by strong ion irradiation doses (see Fig. 8.13(a)). 

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