The effects of temperature and dose-rate variations on the creep of austenitic stainless steels in the dounreay fast reactor

Lewthwaite, G.W.; Mosedale, D.

doi:10.1016/0022-3115(80)90257-3

Cited by 42 publications

(15 citation statements)

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“…Foster noted that the thermal reactor data were derived from lower flux reactors and that Lewthwaite and Mosedale had demonstrated that fast reactor (DFr) creep rates for austenitic steels increase with decreasing dose rate [81]. Thus, Foster's analysis was consistent with their results.…”

Section: Impact Of 59 Ni Effects On Swelling and Irradiation Creepsupporting

confidence: 77%

Void swelling and irradiation creep in light water reactor (LWR) environments

Garner¹

2010

Understanding and Mitigating Ageing in Nuclear Power Plants

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Section: Impact Of 59 Ni Effects On Swelling and Irradiation Creepsupporting

confidence: 77%

Void swelling and irradiation creep in light water reactor (LWR) environments

Garner¹

2010

Understanding and Mitigating Ageing in Nuclear Power Plants

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“…Creep in OSIRIS irradiation conditions is slightly faster than in BOR-60, and a large reduction in the incubation threshold is also noted. This difference can be due either to a spectrum or to a flux effect [14].…”

Section: Temperature Spectrum and Flux Effectmentioning

confidence: 99%

Irradiation creep of SA 304L and CW 316 stainless steels: Mechanical behaviour and microstructural aspects. Part I: Experimental results

Garnier¹,

Bréchet²,

Delnondedieu³

et al. 2011

Journal of Nuclear Materials

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“…The lower dose rate neutron irradiation results in a lower defect density in a given volume per unit time; this may result in a lower number of defect interactions and an increase in the length of defect migration paths compared to higher dose rates. Increasing rates of irradiation creep and swelling with decreasing dose rate have been shown for austenitic steels [30,31]. More recently an increase in irradiation hardening at lower dose rates was shown in ion-irradiated Fe-Cr alloys of similar composition [32]; hereithere it was shown that heightened Cr segregation was the cause of additional hardening in the alloy irradiated with the lowest dose rate.…”

Section: The Effect Of Dose Ratementioning

confidence: 93%

Mechanical properties and plasticity size effect of Fe-6%Cr irradiated by Fe ions and by neutrons

Hardie

Odette

et al. 2016

Journal of Nuclear Materials

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This study compares the effects of ion and neutron irradiation on Fe 6%Cr irradiated to the same dose and at the same temperature by these two methods, and compared with unirradiated material. In recent work reported elsewhere, the materials were characterised by Transmission Electron Microscopy (TEM) and Atom Probe Tomography (APT). This paper reports further investigation of the alloy using nanoindentation and micromechanical testing. Irradiated and un-irradiated micro-cantilevers with a wide range of dimensions were used to study the interrelationships between irradiation hardening and size effects in small-scale plasticity. TEM and APT results identified that the dislocation loop densities were ~2.9x1022m-3 for the neutron irradiated material and only ~1.4x1022m-3 for the ion irradiated material. Cr segregation to loops was only found for the neutron-irradiated material. The nanoindentation hardness increase due to neutron irradiation was 3 GPa, and that due to ion irradiation 1 GPa. The differences between the effects of the two irradiation types are discussed, taking into account inconsistencies in damage calculations, and the differences in PKA spectra, dose rate and transmutation products for the two irradiation types. Nanoindentation was conducted with an MTS NANO Indenter XP (MTS NANO Oak Ridge Tennessee, USA) with a single Berkovich tip; the tip shape was calibrated before each test series. The "continuous stiffness measurement" (CSM) indentation and analysis method [7] was used to make at least 16 indents with a depth of 1000 nm in each sample, in arrays with a indent-to-indent spacing of 40 µm. The amplitude and frequency of the CSM technique was 2 nm and 45 Hz respectively. Due to the small grain size of the samples, data from each indent series, averaged across all indents, includes the response of several grains. Micro-cantilevers were manufactured by Focused Ion Beam (FIB) milling in the un-irradiated and ion irradiated material using a Zeiss Auriga FIB/SEM dual beam system in the Department of Materials, Oxford University. Micro-cantilevers were manufactured in the neutron irradiated material using the 'hot' FEI Quanta dual beam microscope at the Center for Advanced Energy Studies in Idaho Falls (USA). The following test specimens were produced: i. Neutron irradiated sample-66 cantilevers with cross-sectional heights from 0.82 to 7.30 µm (figure 3). ii. Ion irradiated sample-30 cantilevers with cross-sectional heights from 0.36 to 2.3 µm iii. Un-irradiated sample-32 cantilevers with cross-sectional heights from 0.53 to 5.11 µm The cantilever beams were FIB milled by using various beam currents depending on the beam size and were finished with lower polishing currents to achieve a geometry with sharp edges. The All beams were measured by stereo-imaging techniques using the principles described in ref. [8]. Tests were conducted using the Nano-XP nanoindenter by bending the beams to a final maximum peak strain (at the lower surface at the beam root), , of ~0.05 and a target strain rate at the beam ...

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The effects of temperature and dose-rate variations on the creep of austenitic stainless steels in the dounreay fast reactor

Cited by 42 publications

References 1 publication

Void swelling and irradiation creep in light water reactor (LWR) environments

Void swelling and irradiation creep in light water reactor (LWR) environments

Irradiation creep of SA 304L and CW 316 stainless steels: Mechanical behaviour and microstructural aspects. Part I: Experimental results

Mechanical properties and plasticity size effect of Fe-6%Cr irradiated by Fe ions and by neutrons

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