Strain hardening and plastic instability properties of austenitic stainless steels after proton and neutron irradiation

Byun, Thak Sang; Farrell, K.; Lee, E.H.; Hunn, John D.; Mansur, L.K.

doi:10.1016/s0022-3115(01)00651-1

Cited by 56 publications

(50 citation statements)

References 23 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The data indicated that the additional hardening effect from helium (hydrogen) bubbles became significant at helium concentrations above 1 at.%. In the spallation condition, the helium concentration at the highest dose of 11 dpa was about 0.1 at.% [3][4][5]. Thus, some strengthening contribution due to the presence of the gases is expected at the highest dose.…”

Section: Ec316ln Austenitic Stainless Steelmentioning

confidence: 95%

“…At room temperature, the EC316LN stainless steel retained a strong positive strain-hardening capability in the dose range of 0 to 11 dpa [2][3][4][5]. An analysis of the dose dependence of yield stress, instability stress, and fracture stress [5] indicated that the dose to plastic instability at yield would have been about 18 dpa for the EC316LN stainless steel at room temperature.…”

Section: Strain-hardening Behavior In Austenitic Stainless Steelsmentioning

confidence: 99%

“…3 and 4 the tensile data for current EC316LN specimens are overlaid on the trend bands of the database for 316 stainless steels irradiated at temperatures between room temperature and 200°C in fission reactors and tested in the same temperature range [17]. Further, the data are compared with the previous room temperature data for candidate SNS target container materials irradiated in neutron (n) or proton (p) areas of the LANSCE-APT irradiation [2][3][4][5]. At doses below about 1 dpa both yield strength and uniform elongation data for LANSCE irradiations are compatible with the trend bands of the database.…”

Section: Ec316ln Austenitic Stainless Steelmentioning

confidence: 99%

“…A goal exposure for the first target is six months operation, corresponding to a displacement dose of about 5 dpa in the container vessel. In earlier reports [2][3][4][5][6][7] we described the tensile properties of candidate vessel materials after irradiation in the Los Alamos Neutron Scattering Center (LANSCE) accelerator at Los Alamos National Laboratory (LANL) at temperatures in the range 58-160°C. The tensile tests were conducted at ORNL at room temperature.…”

Section: Introductionmentioning

confidence: 99%

“…Austenitic stainless steels showed the most satisfactory results. They retained significant ductility even after irradiation to 11 dpa; the EC316LN steel had positive work hardening and a uniform elongation of 6% [2,5]. Ferritic/martensitic steels displayed prompt instability failures at yield.…”

Section: Introductionmentioning

confidence: 99%

See 4 more Smart Citations

Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation

Byun

Farrell

Lee

et al. 2002

Journal of Nuclear Materials

Self Cite

View full text Add to dashboard Cite

This report presents the tensile properties of EC316LN austenitic stainless steel and 9Cr-2WVTa ferritic/martensitic steel after 800 MeV proton and spallation neutron irradiation to doses in the range 0.54 to 2.53 dpa. Irradiation temperatures were in the range 30 to 100°C. Tensile testing was performed at room temperature (20°C) and 164°C to study the effects of test temperature on the tensile properties. Test materials displayed significant radiation-induced hardening and loss of ductility due to irradiation. The EC316LN stainless steel maintained notable strain-hardening capability after irradiation, while the 9Cr-2WVTa ferritic/martensitic steel posted negative strain hardening. In the EC316LN stainless steel, increasing the test temperature from 20°C to 164°C decreased the strength by 13 to 18% and the ductility by 8 to 36%. The tensile data for the EC316LN stainless steel irradiated in spallation conditions were in line with the values in a database for 316 stainless steels for doses up to 1 dpa irradiated in fission reactors at temperatures below 200 o C. However, extra strengthening induced by helium and hydrogen contents is evident in some specimens irradiated to above about 1 dpa. The effect of test temperature for the 9Cr-2WVTa ferritic/martensitic steel was less significant than for the EC316LN stainless steel.In addition, strain-hardening behaviors were analyzed for EC316LN and 316L stainless steels. The strain-hardening rate of the 316 stainless steels was largely dependent on test temperature. It was estimated that the 316 stainless steels would retain more than 1% true stains to necking at 164 o C after irradiation to 5 dpa. A calculation using reduction of area (RA) measurements and stress-strain data predicted positive strain hardening during plastic instability.

show abstract

Section: Ec316ln Austenitic Stainless Steelmentioning

confidence: 95%