Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78dpa - Concepedia

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Tensile and impact properties of 9Cr tempered martensitic steels and ODS-FeCr alloys irradiated in a fast reactor at 325°C up to 78dpa

60

Citations

8

References

2010

Year

J. Henry, X. Averty, Jesús A. del Alamo

Journal of Nuclear Materials

Materials ScienceEngineeringFast ReactorMechanical EngineeringAlloy DesignImpact PropertiesTempered Martensitic SteelsHigh Strength Low Alloy SteelNuclear ReactorsMechanics Of MaterialsMicrostructure

References

	Year	Citations

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