Published September 1994
| Version v1
Journal article
Proton irradiation induced segregation and phase transformation in AISI 304 and AISI 304L stainless steels
Creators
- 1. Department of Nuclear Engineering, National Tsing Hua Univ., Hsinchu (Taiwan)
Description
Three millimeter diameter TEM discs and miniature tensile specimens were irradiated at 420 and 550 C with 5 MeV H+, to doses ranging from 0.01 to 1 dpa. Energy dispersive X-ray (EDX) analysis indicated that significant radiation-induced solute segregation (RIS) occurred near the grain boundary areas in the irradiated 304 specimens. It was found that the ferrite phase formed in the irradiated 304L specimens, and M23C6 carbides precipitated along the γ-α interfaces. The CERT results for 304 and 304L specimens indicated that after 1 dpa irradiation the fracture surface was characterized by the distinct IGSCC morphology and SCC embrittlement, respectively, in the irradiated region. ((orig.))
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 212-215
- Journal Issue
- pt.A
- Journal Page Range
- p. 476-481.
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 6. international conference on fusion reactor materials (ICFRM-6).
- Dates
- 27 Sep - 1 Oct 1993.
- Place
- Stresa (Italy).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 26009884
- Subject category
- S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBIDES; CRACKS; DISLOCATIONS; ELECTRON MICROSCOPY; EMBRITTLEMENT; FERRITE; FRACTOGRAPHY; FRACTURE PROPERTIES; GRAIN BOUNDARIES; INTERFACES; INTERGRANULAR CORROSION; MEV RANGE 01-10; MICROSTRUCTURE; MORPHOLOGY; PHASE TRANSFORMATIONS; PHYSICAL RADIATION EFFECTS; PRECIPITATION; PROTON BEAMS; RADIATION DOSES; SEGREGATION; SPATIAL DISTRIBUTION; STAINLESS STEEL-304; STAINLESS STEEL-304L; STAINLESS STEELS; STRESS CORROSION; TEMPERATURE DEPENDENCE; TENSILE PROPERTIES; THERMONUCLEAR REACTOR MATERIALS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BEAMS; CARBON ADDITIONS; CARBON COMPOUNDS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DISTRIBUTION; ENERGY RANGE; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; LOW CARBON-HIGH ALLOY STEELS; MATERIALS; MECHANICAL PROPERTIES; MEV RANGE; MICROSCOPY; NICKEL ALLOYS; NUCLEON BEAMS; PARTICLE BEAMS; RADIATION EFFECTS; SEPARATION PROCESSES; STEEL-CR19NI10; STEEL-CR19NI10-L; STEELS