Evaluation of ferritic alloy Fe-2 1/4Cr-1Mo after neutron irradiation: Microstructural development

Conference · Wed Oct 01 04:00:00 EDT 1986

OSTI ID:6858436

Gelles, D S

As part of a program to provide a data base on the bainitic alloy Fe-2-1/4-1Mo for fusion energy applications, microstructural examinations are reported for nine specimen conditions for 2-1/4Cr-1Mo steel which had been irradiated by fast neutrons over the temperature range 390 to 510/sup 0/C. Void swelling is found following irradiation at 400/sup 0/C to 480/sup 0/C. Concurrently dislocation structure and precipitation developed. Peak void swelling, void density, dislocation density and precipitate number density formed at the lowest temperature, approximately 400/sup 0/C, whereas mean void size, and mean precipitate size increased with increasing irradiation temperature. The examination results are used to provide interpretation of in-reactor creep, density change and post irradiation tensile behavior.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76FF02170
• OSTI ID: 6858436
• Report Number(s): HEDL-SA-3398-FP; CONF-860605-37; ON: DE87004350
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
360104 -- Metals & Alloys-- Physical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CREEP
CRYSTAL STRUCTURE
HADRON REACTIONS
HIGH TEMPERATURE
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MECHANICAL PROPERTIES
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
SWELLING
TENSILE PROPERTIES