Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys

Yabuuchi, Kiyohiro; Saito, Masashi; Kasada, Ryuta; Kimura, Akihiko

doi:10.1016/j.jnucmat.2011.05.008

Cited by 33 publications

(10 citation statements)

References 20 publications

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“…6. This non-standard approach of extracting Burgers vectors among a dense population of loops was originally found in works on neutron irradiated Fe-Mn alloys [69]. A recent publication on ion irradiated Fe and Fe-Cr alloys elaborated the method further, where the loss of different variants of ½<111> loops to the foil surface were assigned with a weighted probability [70].…”

Section: Loop Burgers Vectors Analysismentioning

confidence: 99%

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

et al. 2015

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The displacement damage induced in W and W-5 wt.% Re and W-5 wt.% Ta alloys by 2 MeV W + irradiation to doses 3.3×10 17-2.5×10 19 W + /m 2 at temperatures ranging from 300 to 750°C has been characterized by transmission electron microscopy. An automated sizing and counting approach based on Image J (a Java-based image processing program developed at the National Institutes of Health) [1] has been performed for all near-bulk irradiation data. In all cases the damage comprised dislocation loops, mostly of interstitial type, with Burgers vectors b = ½<111> (> 60%) and b = <100>. The diameters of loops did not exceed 20 nm with most being ≤ 6 nm diameter. The loop number density varied between 10 22 and 10 23 loops/m 3. With increasing irradiation temperature, the loop size distributions shifted towards larger sizes, and there was a substantial decrease in loop number densities. The damage microstructure was less sensitive to dose than to temperature. Under the same irradiation conditions, loop number densities in the W-Re and W-Ta alloys were higher than in pure W but loops were smaller. In grains with normals close to z = <001>, loop strings developed in pure W at temperatures ≥ 500°C and doses ≥ 1.2 dpa, but such strings were not observed in the W-Re or W-Ta alloys. However, in other grain orientations complex structures appeared in all materials and dense dislocation networks formed at higher doses.

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Section: Loop Burgers Vectors Analysismentioning

confidence: 99%

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

et al. 2015

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“…Mn is an alloying element, typical content of 0.5-1.5% in RPV steels, and is known from recent data to enhance radiation hardening and embrittlement [13,[17][18][19]. A clear enhancement was observed in high-Cu model steels with increasing Mn from 0.01 to 1.63% [17].…”

Section: Radiation Embrittlement Of Pressure Vessel Steels 31 Radiamentioning

confidence: 99%

“…A clear enhancement was observed in high-Cu model steels with increasing Mn from 0.01 to 1.63% [17]. In simple Fe-Mn alloys, significant enhancement of hardening by Mn addition up to 1.5% was observed after MTR irradiation [19]. P is an impurity element, typical contents below 0.03% in RPV steels, and is known to enhance radiation hardening and embrittlement in low-Cu steels [20,21].…”

Section: Radiation Embrittlement Of Pressure Vessel Steels 31 Radiamentioning

confidence: 99%

Current understanding of radiation-induced degradation in light water reactor structural materials

Fukuya¹

2013

Journal of Nuclear Science and Technology

161

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Current phenomenological knowledge and understanding of mechanisms are reviewed for radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted stress corrosion cracking of core internals of stainless steels. Accumulated test data of irradiated materials in light water reactors and microscopic analyses by using state-of-the-art techniques such as a three-dimensional atom probe and electron backscatter diffraction have significantly increased knowledge about microstructural features. Characteristics of solute clusters and deformation microstructures and their contributions to macroscopic material property changes have been clarified to a large extent, which provide keys to understand in the degradation mechanisms. However, there are still fundamental research issues that merit study for long-term operation of reactors that requires reliable quantitative prediction of radiation-induced degradation of component materials in low-dose rate high-dose conditions.

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“…On the other hand, isolated dislocation loops formed homogeneously in high density in the irradiated Fe-1Mn and Fe-1Ni. For Fe-1Mn, it has been documented that irradiation hardening is enhanced significantly because of high density dislocation loops [16,17]. For Fe-1Ni, the effect of Ni addition on irradiation embrittlement and microstructural evolution was studied in research on the Ni-isotope tailoring (NIT) method on the analogy of He implantation [18,19].…”

Section: Methodsmentioning

confidence: 99%

Effect of alloying elements on irradiation hardening behavior and microstructure evolution in BCC Fe

Yabuuchi

Kasada

Kimura

2013

Journal of Nuclear Materials

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Ion irradiations with 6.4 MeV Fe 3+ were performed on pure-Fe, Fe-1at.%Cr, Fe-1at.%Mn, and Fe-1at.%Ni to a nominal damage of 1 dpa, at a damage rate of 1 × 10-4 dpa/s, at irradiation temperatures of 473, 563, and 673 K. After irradiations at 473 and 563 K, Fe-1Mn and Fe-1Ni showed significant irradiation hardening, which was due to irradiation induced dislocation loops in high density. In pure-Fe, the dislocation loops were localized in the vicinity of dislocations, while those in Fe alloys were distributed rather homogeneously. This can be interpreted in terms of the interaction between alloying element and dislocation strain field. Irradiation at 673 K resulted in the formation of voids in pure-Fe, Fe-1Cr, and Fe-1Mn. We found that chromium suppressed void swelling.

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Neutron irradiation hardening and microstructure changes in Fe–Mn binary alloys

Cited by 33 publications

References 20 publications

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

Current understanding of radiation-induced degradation in light water reactor structural materials

Effect of alloying elements on irradiation hardening behavior and microstructure evolution in BCC Fe

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