Response to annealing and reirradiation of AISI 304L stainless steel following initial high-dose neutron irradiation in EBR-II. [LMFBR]

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:6482003

Porter, D L; McVay, G L; Walters, L C

The object of this study was to measure the stability of irradiation-induced microstructure upon annealing and, by selectively annealing out some of these features and reirradiating the material, it was expected that information could be gained concerning the role of microstructural changes in the void swelling process. Transmission electron microscopic examinations of isochronally annealed (200 to 1050/sup 0/C) AISI 304L stainless steel, which had been irradiated at approximately 415/sup 0/C to a fast (E > 0.1 MeV) neutron fluence of approximately 5.1 x 10/sup 26/n/m/sup 2/, verified that the two-stage hardness recovery with temperatures was related to a low temperature annealing of dislocation structures and a higher temperature annealing of voids and solute redistribution.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 6482003
• Report Number(s): CONF-800609-17; TRN: 81-011195
• Resource Relation: Conference: 10. international symposium on effects of radiation on materials, Savannah, GA, USA, 3 Jun 1980
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
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REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
STAINLESS STEEL-304L
ANNEALING
MICROSTRUCTURE
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEAT TREATMENTS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
NICKEL ALLOYS
RADIATION EFFECTS
REACTORS
STAINLESS STEELS
STEELS
210500* - Power Reactors
Breeding
360106 - Metals & Alloys- Radiation Effects