1996
DOI: 10.1016/s0022-3115(96)00327-3
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Low-activation ferritic and martensitic steels for fusion application

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Cited by 394 publications
(161 citation statements)
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“…As mentioned previously, the literature suggests that 7-9 wt%Cr alloys show a lesser tendency to irradiation hardening and have a better resistance to radiation damage [5,29]. However, in the present work we do not find a clear optimum in chromium concentration with respect to ductility, particularly when the calculations are done with all the other variables kept constant.…”
Section: Chromium Concentrationcontrasting
confidence: 47%
“…As mentioned previously, the literature suggests that 7-9 wt%Cr alloys show a lesser tendency to irradiation hardening and have a better resistance to radiation damage [5,29]. However, in the present work we do not find a clear optimum in chromium concentration with respect to ductility, particularly when the calculations are done with all the other variables kept constant.…”
Section: Chromium Concentrationcontrasting
confidence: 47%
“…[16][17][18] F-82H has been evaluated under an International Energy Agency Collaborative Program. 2,19) It is very important to assess the stability of TaC particles in order to evaluate the behavior of the fusion materials in service. Therefore, F-82H was tempered in a wide range ISIJ International, Vol.…”
Section: Introductionmentioning
confidence: 99%
“…For all these reasons, the community focuses on model irradiation experiments performed on Fe-Cr model alloys using alternative irradiation sources. Alloys containing more than 12% Cr are of particular interest in nuclear plants because of their corrosion resistance, but they are prone to embrittlement due to α precipitation below 500°C [6,7].…”
mentioning
confidence: 99%