Microstructural stability of fast reactor irradiated 10 to 12% Cr ferritic-martensitic stainless steels
- AERE Harwell, England
The strength and microstructural stability of three 10 to 12% Cr ferritic-martensitic stainless steels have been characterized following fast reactor irradiation to damage levels of 30 displacements per atom (dpa) at temperatures in the range 380 to 615/sup 0/C. Irradiation results in either increases or decreases in room temperature hardness depending on the irradiation temperature. These strength changes can be qualitatively rationalized in terms of the combined effects of irradiation-induced interstitial dislocation loop formation and recovery of the dislocation networks comprising the initial tempered martensite structures. Precipitate evolution in the irradiated steels is associated with the nonequilibrium segregation of the elements nickel, silicon, molybdenum, chromium and phosphorus, brought about by solute-point defect interactions. The principal irradiation-induced precipitates identified are M/sub 6/X, intermetallic chi and sigma phases and also ..cap alpha..' (Cr-rich ferrite). The implications of the observed microstructural changes on the selection of martensitic stainless steels for fast reactor wrapper applications are briefly considered.
- OSTI ID:
- 5709818
- Report Number(s):
- CONF-820628-
- Journal Information:
- Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States) Vol. 782; ISSN ASTTA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
BARYONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CRYSTAL DEFECTS
CRYSTAL STRUCTURE
DISLOCATIONS
ELEMENTARY PARTICLES
FAST NEUTRONS
FERMIONS
FERRITIC STEELS
HADRONS
IRON ALLOYS
IRON BASE ALLOYS
LINE DEFECTS
MICROSTRUCTURE
NEUTRONS
NUCLEONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SEGREGATION
STEELS
TEMPERATURE DEPENDENCE