Research output: Contribution to journal › Article › peer-review
Stability of the structure and properties of an ultrafine-grained Cr-Ni steel irradiated with neutrons in nuclear reactor core conditions. / Shamardin, V. K.; Abramova, M. M.; Bulanova, T. M.; Karsakov, A. A.; Fedoseev, A. E.; Obukhov, A. V.; Valiev, R. Z.; Alexandrov, I. V.; Raab, G. I.; Enikeev, N. A.
In: Materials Science and Engineering A, Vol. 712, 18.01.2018, p. 365-372.Research output: Contribution to journal › Article › peer-review
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TY - JOUR
T1 - Stability of the structure and properties of an ultrafine-grained Cr-Ni steel irradiated with neutrons in nuclear reactor core conditions
AU - Shamardin, V. K.
AU - Abramova, M. M.
AU - Bulanova, T. M.
AU - Karsakov, A. A.
AU - Fedoseev, A. E.
AU - Obukhov, A. V.
AU - Valiev, R. Z.
AU - Alexandrov, I. V.
AU - Raab, G. I.
AU - Enikeev, N. A.
PY - 2018/1/18
Y1 - 2018/1/18
N2 - An ultrafine-grained (UFG) austenite Cr-Ni stainless steel was produced by equal-channel angular pressing. The UFG samples were irradiated in a research nuclear reactor up to damaging doses of 12 and 15 dpa at 350 °C and 450 °C, respectively. The post-irradiation examination featured in this work covers microstructural and mechanical property changes at test temperatures of 20–650 °C. Microstructural studies showed that the concentration of Frank loops was considerably lower in the UFG steel compared to in the coarse-grained material. It was also found that irradiation resulted in precipitation of α-phase in triple junctions of the UFG steel. The post-irradiation examination of mechanical properties testified that the UFG steel exhibited lower irradiation hardening and higher strength compared to the coarse-grained material in the entire testing temperatures range, and improved ductility when tested at 500–650 °C. In summary, we testified that microstructure refinement of an austenite stainless steel down to UFG scale led to enhancement of its resistance to neutron irradiation at elevated temperatures.
AB - An ultrafine-grained (UFG) austenite Cr-Ni stainless steel was produced by equal-channel angular pressing. The UFG samples were irradiated in a research nuclear reactor up to damaging doses of 12 and 15 dpa at 350 °C and 450 °C, respectively. The post-irradiation examination featured in this work covers microstructural and mechanical property changes at test temperatures of 20–650 °C. Microstructural studies showed that the concentration of Frank loops was considerably lower in the UFG steel compared to in the coarse-grained material. It was also found that irradiation resulted in precipitation of α-phase in triple junctions of the UFG steel. The post-irradiation examination of mechanical properties testified that the UFG steel exhibited lower irradiation hardening and higher strength compared to the coarse-grained material in the entire testing temperatures range, and improved ductility when tested at 500–650 °C. In summary, we testified that microstructure refinement of an austenite stainless steel down to UFG scale led to enhancement of its resistance to neutron irradiation at elevated temperatures.
KW - Austenite stainless steel
KW - Mechanical properties
KW - Microstructure
KW - Neutron irradiation
KW - Ultrafine-grained materials
KW - STAINLESS-STEEL
KW - BEHAVIOR
KW - RESISTANCE
KW - ION IRRADIATION
KW - MICROSTRUCTURE
KW - NANOSTRUCTURED MATERIALS
UR - http://www.scopus.com/inward/record.url?scp=85036625767&partnerID=8YFLogxK
U2 - 10.1016/j.msea.2017.11.096
DO - 10.1016/j.msea.2017.11.096
M3 - Article
AN - SCOPUS:85036625767
VL - 712
SP - 365
EP - 372
JO - Materials Science and Engineering: A
JF - Materials Science and Engineering: A
SN - 0921-5093
ER -
ID: 16948656