Tensile properties and swelling of 20%-cold-worked Type 316 stainless steel irradiated in HFIR
Immersion density and elevated-temperature tensile properties were determined on 20%-cold-worked type 316 stainless steel irradiated in the HFIR at approximately 285, 370, 470, 560, and 620/sup 0/C to fluences of 1.8 to 6.2 x 10/sup 26/ neutrons/m/sup 2/ (> 0.1 MeV), which resulted in displacement damage levels of 16 to 54 dpa and helium concentrations of 900 to 3300 at. ppM. Tensile tests were done at temperatures near the estimated irradiation temperatures. Swelling increased with increasing irradiation temperature to a maximum of 2.1% at 620/sup 0/C. Irradiation at the lowest temperature (285 and 370/sup 0/C) increased the strength. At the higher irradiation temperatures, the strength decreased during irradiation. Ductility generally reflected the strength behavior: an increase in strength resulted in a descrease in ductility. When the present data are compared with previously published data, there is good agreement with one exception. Previous experiments showed a large decrease in ductility when irradiated at 600/sup 0/C and tested at 575/sup 0/C that was not observed in the present tests. There was also good agreement between HFIR-irradiated steel and literature data for EBR-II-irradiated steel.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 6849206
- Report Number(s):
- CONF-840604-13; ON: DE84014080
- Resource Relation:
- Conference: 12. international symposium on effects of radiation on materials, Williamsburg, VA, USA, 18 Jun 1984; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
STAINLESS STEEL-316
SWELLING
TENSILE PROPERTIES
DUCTILITY
ELONGATION
EXPERIMENTAL DATA
HFIR REACTOR
HIGH TEMPERATURE
NEUTRON REACTIONS
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
ENRICHED URANIUM REACTORS
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
360103* - Metals & Alloys- Mechanical Properties
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