Effects of large concentrations of helium on the mechanical properties of neutron-irradiated stainless steel
Tensile and creep properties have been determined on specimens of type 316 stainless steel irradiated in the High Flux Isotope Reactor in the range 380 to 785$sup 0$C. Irradiation of type 316 in this reaction partially simulates fusion reactor irradiation, with displacement damage levels up to 120 dpa and helium contents up to 6000 appM achieved in two years. Samples irradiated in the annealed condition to about 100 dpa and 4000 appM helium showed an increased yield strength between 350 and 600$sup 0$C and, except at 350$sup 0$C, a reduced ultimate tensile strength compared with values for the unirradiated material. Samples irradiated in the 20 percent-cold-worked condition showed decreases in both yield and ultimate tensile strengths at all test temperatures. The irradiated samples of both annealed and cold-worked material exhibited little strain hardening. Total elongations were small and became zero for tests at 650$sup 0$C. Tensile tests at 575$sup 0$C and creep-rupture tests at 550$sup 0$C showed strong effects of fluence on strength and ductility for helium contents above about 30 appM. Optical metallography showed extensive carbide precipitation at all temperatures and precipitation of a second phase, believed to be sigma, at the high temperatures. (NL)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- NSA Number:
- NSA-33-023806
- OSTI ID:
- 4051008
- Journal Information:
- J. Nucl. Mater., v. 58, no. 2, pp. 171-184, Journal Name: J. Nucl. Mater., v. 58, no. 2, pp. 171-184; ISSN JNUMA
- Country of Publication:
- Netherlands
- Language:
- English
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Related Subjects
360106* --Materials--Metals & Alloys--Radiation Effects
CREEP
DUCTILITY
FAST NEUTRONS
HELIUM
HFIR REACTOR
HIGH TEMPERATURE
IRRADIATION
N50240* --Metals
Ceramics
& Other Materials--Metals & Alloys--Radiation Effects
NEUTRON FLUENCE
NEUTRON FLUX
PRECIPITATION
QUANTITY RATIO
THERMAL NEUTRONS
VERY HIGH TEMPERATURE
YIELD STRENGTH