Nanostructure evolution in ODS Eurofer steel under irradiation up to 32 dpa

Рогожкин, С. В.; Орлов, Н. Н.; Aleev, A. A.; Залужный, А. Г.; Kozodaev, M. A.; Kuibeda, R. P.; Kulevoy, T. V.; Никитин, А. А.; Chalykh, B. B.; Lindau, R.; Möslang, A.; Vladimirov, P.

doi:10.1134/s0031918x15010093

Cited by 15 publications

(3 citation statements)

References 28 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…ODS-Eurofer97 has also shown formation of internal cavities along with complete amorphisation of the nano-dispersoids after fast neutron irradiations in the BOR-60 reactor at 250, 350 and 450 • C up to 16.2 dpa, reported by Klimenkov et al [221], thereby suggesting qualitatively similar observations between relatively coarse oxides of PM2000 versus relatively finer oxides in ODS-Eurofer97. Moreover, APT results from Rogozhkin et al on BOR-60-irradiated ODS-Eurofer97 (330 • C, 32 dpa) also show chemical changes in the nano-dispersoids due to irradiation-chemistry of the particles evolves by loss of V and progressive increase of Y concentration hypothesised due to dissolution of particles >10 nm in diameter [222,228]. Structural deterioration including formation of internal cavities in the nano-dispersoids is known for neutronirradiated MA956 (328 • C, 4.36 dpa) [199].…”

Section: Potential Causes Of Lthementioning

confidence: 93%

“…Because oxide particles act as point-defect sinks, any changes to the nano-dispersoid microstructure will affect the overall radiation tolerance of the alloy in the entire operating temperature range for FW/B structures. The oxide particle stability, recently reviewed in [216], has been extensively researched using neutrons [194,196,199,204,205,[217][218][219][220][221][222][223][224][225][226][227][228][229][230], ions [219, and electron irradiations [261,262] in a variety of ODS steels. Extensive ion irradiation literature exists on a wide range of ODS steels where nano-dispersoids are reported to be stable over the irradiation temperature and dose ranges of RT-835 • C and ion doses from ∼2 to 200 dpa [205, 233, 234, 237, 240, 243, 247-249, 251, 259, 263].…”

Section: Potential Causes Of Lthementioning

confidence: 99%

See 1 more Smart Citation

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

et al. 2022

View full text Add to dashboard Cite

Reduced activation ferritic-martensitic (RAFM) and oxide dispersion strengthened (ODS) steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. Performance of these steels will deteriorate in-service due to neutron damage and transmutation-induced gases like helium/hydrogen at elevated operating temperatures. Here, after highlighting the operating conditions of fusion reactor concepts and a brief overview, the major irradiation-induced degradation challenges associated with RAFM/ODS steels are discussed. Their long-term degradation scenarios such as (i) low temperature hardening-embrittlement (LTHE) - including dose-temperature dependent yield stress, tensile elongations, necking ductility, test temperature effect on hardening, Charpy impact ductile to brittle transition temperature and fracture toughness, (ii) inter-mediate temperature cavity swelling, (iii) the effect of helium on LTHE and cavity swelling, (iv) irradiation creep and (v) tritium management issues are reviewed. The potential causes of LTHE are discussed that highlights need for advanced characterization techniques. Mechanical properties including tensile/Charpy impact of RAFM and ODS steels are compared to show that current generation of ODS steels also suffer from LTHE, and they can show irradiation hardening up to high temperatures, ~400-500 °C. To minimize this, future ODS steel development for FW/B specific application should target materials with lower Cr concentration (to minimize α’) and minimize other elements that could form embrittling phases under irradiation. RAFM steel designing activities targeting improvements in creep and LTHE are reviewed. The need to better understand synergistic effects of helium on thermo-mechanical properties in the entire temperature range of FW/B is highlighted. Because fusion operating conditions will be complex including stresses due to magnetic field, primary loads like coolant pressure, secondary loads from thermal gradients, and due to spatial variation in damage levels and gas production rates, an experimentally validated multi-scale modelling approach is suggested as a pathway to future reactor component designing such as for the fusion neutron science facility

show abstract

Section: Potential Causes Of Lthementioning

confidence: 93%

Section: Potential Causes Of Lthementioning

confidence: 99%

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

et al. 2022

View full text Add to dashboard Cite

show abstract

“…The test temperatures of irradiated Eurofer 97 and ODS Eurofer were 200 °C and 330 °C respectively. Nanoscale reconstruction of ferritic-martensitic steels under heavy ion irradiation was also studied with heavy ion irradiation [22,23]. Atom probe specimens with an apex radius of ~ 50 nm were used for the irradiation experiment.…”

Section: Methodsmentioning

confidence: 99%

Evolution of microstructure in advanced ferritic-martensitic steels under irradiation: the origin of low temperature radiation embrittlement

et al. 2016

Self Cite

View full text Add to dashboard Cite

Advanced reduced activation ferritic/martensitic steels and oxide dispersion-strengthened steels exhibit significant radiation embrittlement under low temperature neutron irradiation. In this study we focused on atom probe tomography (APT) of Eurofer97 and ODS Eurofer steels irradiated with neutrons and heavy ions at low temperatures. Previous TEM studies revealed dislocation loops in the neutron-irradiated f\m steels. At the same time, our APT showed early stages of solid solution decomposition. High density (10 24 m -3 ) of ~3-5 nm clusters enriched in chromium, manganese, and silicon atoms were found in Eurofer 97 irradiated in BOR-60 reactor to 32 dpa at 332°C. In this steel irradiated with Fe ions up to the dose of 24 dpa, pair correlation functions calculated using APT data showed the presence of Cr-enriched pre-phases.APT study of ODS Eurofer found a significant change in the nanocluster composition after neutron irradiation to 32 dpa at 330 °C and an increase in cluster number density. APT of ODS steels irradiated with Fe ions at low temperatures revealed similar changes in nanoclusters.These results suggest that irradiation-induced nucleation and evolution of very small precipitates may be the origin of low temperature radiation embrittlement of f\m steels.

show abstract