Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Tensile properties of 20% cold-worked titanium-modified type 316 stainless steel irradiated in HFIR

Conference ·
OSTI ID:6849736
;
An alloy of type 316 stainless steel with the addition of 0.23% Ti (316 + Ti) has been irradiated in the 20% cold-worked condition in the HFIR (a mixed fast and thermal neutron spectrum reactor) and tested near the irradiation temperature in the range of 300 to 600/sup 0/C. Tensile tests were performed following irradiation to fluence levels of 0.63 to 2.1 x 10/sup 26/ n/m/sup 2/ (E > 0.1 MeV) and helium levels of 200 to 1000 at. ppM. The 316 + Ti exhibited higher strength and lower ductility than similarly irradiated type 316 stainless steel (316 SS). However, the tensile elongation of 316 + Ti tends to saturate with increasing fluence at 575/sup 0/C whereas the elongation of 316 SS continues to fall for the fluences investigated. Reduction of area is similar for the two alloys, and 316 + Ti shows completely ductile rupture at 450/sup 0/C and below. The differences in strength and ductility are attributed to the influence of TiC precipitates trapping helium in the matrix.
Research Organization:
Oak Ridge National Lab., TN (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
6849736
Report Number(s):
CONF-810831-95; ON: DE82020906
Country of Publication:
United States
Language:
English

Similar Records

Tensile properties and swelling of 20%-cold-worked Type 316 stainless steel irradiated in HFIR
Technical Report · Sat Dec 31 23:00:00 EST 1983 · OSTI ID:6849206
Influence of neutron irradiation at 55/sup 0/C on the properties of austenitic stainless steels
Conference · Wed Dec 31 23:00:00 EST 1980 · OSTI ID:6346300
Tensile properties of type 316 stainless steel irradiated in a simulated fusion reactor environment
Conference · Sun Dec 31 23:00:00 EST 1978 · OSTI ID:6259271

Related Subjects

36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
BARYON REACTIONS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
DATA
DUCTILITY
ELEMENTS
ELONGATION
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FLUIDS
GASES
HADRON REACTIONS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HELIUM
HFIR REACTOR
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
MATERIALS
MECHANICAL PROPERTIES
METALS
MOLYBDENUM ALLOYS
NEUTRON REACTIONS
NICKEL ALLOYS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUMERICAL DATA
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
RARE GASES
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
TANK TYPE REACTORS
TENSILE PROPERTIES
TEST REACTORS
THERMAL REACTORS
TITANIUM
TITANIUM ADDITIONS
TITANIUM ALLOYS
TRANSITION ELEMENTS
TRAPPING
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELD STRENGTH