Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels

Kupriiyanova, Y.E.; Брык, В.В.; Borodin, O.V.; Kalchenko, А.S.; Voyevodin, V.N.; Tolstolutskaya, G.D.; Garner, F.А.

doi:10.1016/j.jnucmat.2015.07.012

Cited by 52 publications

(24 citation statements)

References 30 publications

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“…Other non-rastered ion studies conducted on pure iron [36] and several ferritic-martensitic alloys [33,57,58] were observed to develop a post-transient swelling rate of ~0.2%/dpa, in agreement with the neutron-induced swelling rate. Two of these observations are shown in Fig 7. These observations of 0.2%/dpa were made on two different accelerators, operating at two different conditions of dpa rate and ion energy, one located in the Ukraine and the other in Texas, signaling the possible reproducibility of this swelling rate in both ion and neutron irradiations.…”

Section: Note Insupporting

confidence: 62%

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Gigax

Chen

Kim

et al. 2016

Journal of Nuclear Materials

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Ferritic-martensitic alloys are required for advanced reactor components to survive 500-600 neutron-induced dpa. Ion-induced void swelling of ferritic-martensitic alloy T91 in the quenched and tempered condition has been studied using a defocused, non-rastered 3.5 MeV Fe-ion beam at 475°C to produce damage levels up to 1000 peak displacements per atom (dpa). The high peak damage level of 1000 dpa is required to reach 500-600 dpa level due to injected interstitial suppression of void nucleation in the peak dpa region, requiring data extraction closer to the surface at lower dpa levels. At a relatively low peak damage level of 250 dpa, voids began to develop, appearing first in the near-surface region. With increasing ion fluence, swelling was observed deeper in the specimen, but remained completely suppressed in the back half of the ion range, even at 1000 peak dpa. The local differences in dpa rate in the front half of the ion range induce an "internal temperature shift" that strongly influences the onset of swelling, with shorter transient regimes resulting from lower dpa rates, in agreement not only with observations in neutron irradiation studies but also in various ion irradiations. Swelling was accompanied by radiation-induced precipitation of Cu-rich and Si, Ni, Mn-rich phases were observed by atom probe tomography, indicating concurrent microchemical evolution was in progress. In comparison to other ferritic-martensitic alloys during ion irradiation, T91 exhibits good swelling resistance with a swelling incubation period of about 400 local dpa.

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Section: Note Insupporting

confidence: 62%

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Gigax

Chen

Kim

et al. 2016

Journal of Nuclear Materials

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“…Furthermore, it has been argued, in particular by F. Garner, that the low swelling values generally observed in the case of irradiated FM steels, result primarily from a long transient regime of swelling and that when the transient regime terminates, the steady state swelling rate of FM steels could be about 0.2%/dpa [3]. Indeed, ion irradiation experiments of FM steels up to very high doses have shown a steady state swelling regime whose slope was found to be close to 0.2%/dpa [21].…”

Section:  Void Microstructurementioning

confidence: 98%

Mechanical and microstructural analysis of an EM10 wrapper tube after neutron irradiation in Phénix

Tissot

Gavoille

Verhaeghe

et al. 2021

Journal of Nuclear Materials

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The 9Cr-1Mo tempered martensitic steel was irradiated with fast neutrons in the French Phénix reactor. Mechanical tests, density measurement as well as microstructural investigations were carried out following irradiation up to 155 dpa in the temperature range 386°C -525°C. Tensile, elongation and impact properties were only slightly modified by irradiation. Microstructural investigations revealed the presence of cavities, however the resulting swelling was low (0.1%). In most cases, the dislocation microstructure was arranged in a network. Nevertheless, some large loops were observed after irradiation at 398°C to 112 dpa. Overall, the EM10 steel showed excellent radiation resistance, which confirmed that this steel is an attractive wrapper candidate material for future sodium-cooled GEN IV fast reactors.

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“…A challenge for developing advanced nuclear systems, such as fusion reactors, Generation IV fission reactors, and accelerator-driven spallation (ADS) devices, is the deep understanding of the complicated irradiation damage mechanisms in irradiation resistant materials [1,2,3,4]. Reduced-activation ferritic/martensitic (RAFM) steels are considered as prime candidate structural materials for advanced nuclear systems, owing to their excellent mechanical properties, microstructural stability, and irradiation resistance [5,6,7]. However, the properties of the RAFM steels will degrade when they are exposed to conditions of high energy neutron irradiations, such as 14 MeV for fusion reactors and hundreds of MeV for ADS devices.…”

Section: Introductionmentioning

confidence: 99%

“…Actually, hydrogen played an important role in the microstructure evolution. Kupriiyanova et al found that the co-implantation of hydrogen resulted in more swelling than heavy-ion implantation alone [7]. In RAFM steels, there are some studies concerning the role of hydrogen in microstructures, most of which are focused on bubbles [9,15], whilst there are few studies on dislocation loops.…”

Section: Introductionmentioning

confidence: 99%

Evolution of Dislocation Loops Induced by Different Hydrogen Irradiation Conditions in Reduced-Activation Martensitic Steel

et al. 2018

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Hydrogen can be induced in various ways into reduced-activation ferritic/martensitic (RAFM) steels when they are used as structural materials for advanced nuclear systems. However, because of the fast diffusion of hydrogen in metals, the effect of hydrogen on the evolution of irradiation-induced defects was almost neglected. In the present work, the effect of hydrogen on the evolution of dislocation loops was investigated using a transmission electron microscope. Specimens of reduced-activation ferritic/martensitic (RAFM) steels were irradiated with hydrogen ions to 5 × 1020 H+ • m−2 at 523–823 K, and to 1 × 1020 H+ • m−2 − 5 × 1020 H+ • m−2 at 723 K. The experimental results reveal that there is an optimum temperature for dislocation loop growth, which is ~723 K, and it is greater than the reported values for neutron irradiations. Surprisingly, the sizes of the loops produced by hydrogen ions, namely, 93 nm and 286 nm for the mean and maximum value, respectively, at the peak dose of 0.16 dpa under 723 K, are much larger than that produced by neutrons and heavy ions at the same damage level and temperature. The results indicate that hydrogen could enhance the growth of loops. Moreover, 47.3% 12 a0 <111> and 52.7% a0 <100> loops were observed at 523 K, but 12 a0 <111> loops disappeared and only a0 <100> loops existed above 623 K. Compared with the neutron and ion irradiations, the presence of hydrogen promoted the formation of a0 <100> loops.

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Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels

Cited by 52 publications

References 30 publications

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

Mechanical and microstructural analysis of an EM10 wrapper tube after neutron irradiation in Phénix

Evolution of Dislocation Loops Induced by Different Hydrogen Irradiation Conditions in Reduced-Activation Martensitic Steel

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