Role of Scale Factor During Tensile Testing of Small Specimens

Gussev, Maxim N.; Busby, Jeremy T.; Field, Kevin G.; Sokolov, Mikhail A.; Gray, Seán

doi:10.1520/stp157620140013

Cited by 35 publications

(26 citation statements)

References 28 publications

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“…Miniature sub-size specimens for post neutron radiation testing have a long story and are widely used for investigating mechanical properties and deformation-hardening behavior of metals and alloys [32,33], weldments [34], nanostructured materials, and different composites. A variety of different sizes and geometries are used in nuclear materials science [33,35,36], with new geometries and testing methods being constantly developed [37].…”

Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

“…A variety of different sizes and geometries are used in nuclear materials science [33,35,36], with new geometries and testing methods being constantly developed [37]. Historically, for the irradiation at the High-Flux Isotope Reactor (HFIR) two miniature tensile specimen geometries are most often used, SS-3 and SS-J type [32,33]. For many material classes, these geometries provide acceptable mechanical properties compared to standard specimens [32].…”

Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

“…Historically, for the irradiation at the High-Flux Isotope Reactor (HFIR) two miniature tensile specimen geometries are most often used, SS-3 and SS-J type [32,33]. For many material classes, these geometries provide acceptable mechanical properties compared to standard specimens [32]. However, the post-irradiation activity level is usually too high and limits the postirradiation testing within a hot cell facility only, especially when moderate to high damage dose (dpa) samples are of interest.…”

Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

See 2 more Smart Citations

First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

Field

Gussev

et al. 2015

Self Cite

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Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

Section: Design Methodology For Miniaturized Specimenmentioning

confidence: 99%

See 1 more Smart Citation

First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

Field

Gussev

et al. 2015

Self Cite

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“…The major impurities in the non-irradiated material are 10 ppm O, <10 ppm N, 20 ppm C, <5 ppm S, 3 ppm H, and 140 ppm Cu [23]. SS-J3 tensile test specimens [24] were machined directly from the procured tungsten rod and then exposed to neutron irradiation in the flux trap facility in the High Flux Isotope Reactor (HFIR) at ORNL, USA. The irradiation conditions are summarized in Table 2.…”

Section: Materials and Neutron Irradiationmentioning

confidence: 99%

Irradiation hardening of pure tungsten exposed to neutron irradiation

Koyanagi

Fukuda

et al. 2016

Journal of Nuclear Materials

215

103

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Pure tungsten samples have been neutron irradiated in HFIR at 90~850°C to 0.03~2.2 dpa. A dispersed barrier hardening model informed by the available microstructure data has been used to predict the hardness. Comparison of the model predictions and the measured Vickers hardness reveals the dominant hardening contribution at various irradiation conditions. For tungsten samples irradiated in HFIR, the results indicate that voids and dislocation loops contributed to the hardness increase in the low dose region (< 0.3 dpa), while the formation of intermetallic second phase precipitation, resulting from transmutation, dominates the radiation-induced strengthening beginning with a relatively modest dose (> 0.6 dpa). The precipitate contribution is most pronounced for the HFIR irradiations, whereas the radiation-induced defect cluster microstructure can rationalize the entirety of the hardness increase observed in tungsten irradiated in the fast neutron spectrum of Joyo and the mixed neutron spectrum of JMTR.

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“…The deviation in the absolute values for total elongation in this study and that of Yamamoto et al can be attributed to the differences in the test specimens used. For example, Gussev et al and Byun et al have shown strong dependencies between the thickness-to-width ratio and the reported total elongation values[21,22].…”

mentioning

confidence: 99%

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

Field

Briggs

Sridharan

et al. 2017

Journal of Nuclear Materials

Self Cite

127

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The development and understanding of the mechanical properties of neutron-irradiated FeCrAl alloys is increasingly a critical need as these alloys continue to become more mature for nuclear reactor applications. This study focuses on the mechanical properties of model FeCrAl alloys and of a commercial FeCrAl alloy neutron-irradiated to up to 13.8 displacements per atom (dpa) at irradiation temperatures between 320 and 382°C. Tensile tests were completed at room temperature and at 320°C, and a subset of fractured tensile specimens was examined by scanning electron microscopy. Results showed typical radiation hardening and embrittlement indicative of high chromium ferritic alloys with strong chromium composition dependencies at lower doses. At and above 7.0 dpa, the mechanical properties saturated for both the commercial and model FeCrAl alloys, although brittle cleavage fracture was observed at the highest dose in the model FeCrAl alloy with the highest chromium content (18 wt %). The results suggest the composition and microstructure of FeCrAl alloys plays a critical role in the mechanical response of FeCrAl alloys irradiated near temperatures relevant to light water reactors.

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Role of Scale Factor During Tensile Testing of Small Specimens

Cited by 35 publications

References 28 publications

First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

First Annual Progress Report on Radiation Tolerance of Controlled Fusion Welds in High Temperature Oxidation Resistant FeCrAl Alloys

Irradiation hardening of pure tungsten exposed to neutron irradiation

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys

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