Development of New Construction Materials for Innovative Reactor Installation Designs

Korostelev, A. B.; Evropin, S. V.; Derzhavin, A. G.; Vershinin, I. V.; Goslavskii, O. V.; Romanov, A. N.

doi:10.1007/s10512-021-00741-8

Cited by 8 publications

(3 citation statements)

References 2 publications

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“…At the same time, the use of traditional types of steels and alloys in modern realities of the operation of structural materials in high-temperature nuclear reactors is limited by the temperature conditions of the core, as well as accelerated processes of accumulation of radiation damage during prolonged exposure [1][2][3]. In the case of long-term high-temperature irradiation, traditional methods of stability increase by alloying steels or creating nanostructural inclusions in them, which make it possible to change the properties of binary alloys, are not always effective [4,5]. Under high-dose irradiation, nanostructured inclusions, which are mostly metastable, can destabilize the irradiated material due to thermal effects, leading to accelerated destruction and embrittlement.…”

Section: Introductionmentioning

confidence: 99%

Study of the Mechanisms of Radiation Softening and Swelling upon Irradiation of TiTaNbV Alloys with He2+ Ions with an Energy of 40 keV

et al. 2023

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This paper presents simulation results of the ionization losses of incident He2+ ions with an energy of 40 keV during the passage of incident ions in the near-surface layer of alloys based on TiTaNbV with a variation of alloy components. For comparison, data on the ionization losses of incident He2+ ions in pure niobium, followed by the addition of vanadium, tantalum, and titanium to the alloy in equal stoichiometric proportions, are presented. With the use of indentation methods, the dependences of the change in the strength properties of the near-surface layer of alloys were determined. It was established that the addition of Ti to the composition of the alloy leads to an increase in resistance to crack resistance under high-dose irradiation, as well as a decrease in the degree of swelling of the near-surface layer. During tests on the thermal stability of irradiated samples, it was found that swelling and degradation of the near-surface layer of pure niobium affects the rate of oxidation and subsequent degradation, while for high-entropy alloys, an increase in the number of alloy components leads to an increase in resistance to destruction.

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Section: Introductionmentioning

confidence: 99%

Study of the Mechanisms of Radiation Softening and Swelling upon Irradiation of TiTaNbV Alloys with He2+ Ions with an Energy of 40 keV

et al. 2023

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“…As a ferritizing element, the increase in Si addition increases the Cr equivalent, which ultimately affects the content of δ ferrite in the weld metal. Because the contents of Cr and Ni in the 15Cr-9Ni-Nb steel are lower than the common austenitic stainless steel, the austenitic stability of 15Cr-9Ni-Nb austenitic stainless steel will also be reduced [14]. The martensite transformation temperature will rise, and trace changes in elements may have a significant effect on the microstructure of the 15Cr-9Ni-Nb steel weld metal.…”

Section: Introductionmentioning

confidence: 99%

“…The temperature of the SHT is required to be higher than the sensitization temperature to avoid the formation of M 23 C 6 carbide. The austenite in 15Cr-9Ni-Nb steel is metastable at room temperature [14], and the effect of C reduction in the matrix during the SHT on the microstructure and mechanical properties of the weld metal is worth investigating in detail. In addition, precipitation during SHT can also have an impact on the mechanical properties of the weld metal [16,17].…”

Section: Introductionmentioning

confidence: 99%

Effects of Stabilization Heat Treatment on Microstructure and Mechanical Properties of Si-Bearing 15Cr–9Ni–Nb Austenitic Stainless Steel Weld Metal

Chen

et al. 2022

Acta Metall. Sin. (Engl. Lett.)

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Two 15Cr-9Ni-Nb austenitic stainless steel weld metals with 2.5% Si and 3.5% Si (namely 2.5Si and 3.5Si samples, respectively) were designed and prepared through tungsten inert gas (TIG) welding and then hold at 800 °C or 900 °C for 3 h for stabilization. The microstructure and mechanical properties were investigated both for the as-welded and after-stabilization heat treatment (SHT) weld metals. There are 3.0-4.0% martensite and 2.5-3.5% δ ferrite in the 2.5Si as-welded weld metal and 6.0-7.0% δ ferrite in the 3.5Si as-welded weld metal. After SHT, a large amount of martensite formed in the 2.5Si weld metal, and δ → γ transition occurred during the SHT process both for the 2.5Si and 3.5Si weld metals. There were a large amount of coarse NbC and few nanoscale NbC in the as-welded weld metal. During the SHT, a large amount of nanoscale NbC formed in the matrix, while a large number of G phases formed at the austenite grain boundaries and the δ/γ interfaces. The decrease in solid solution C and δ ferrite content led to the decline of the yield strength of the weld metal after SHT. The martensite formed in 2.5Si weld metal after SHT had less effect on strength because of its low carbon content. The G phases formed during the SHT reduced the impact energy of the weld metal because it promoted the intergranular fracture, while the δ → γ transition reduced the amount of the δ/γ interfaces and avoided the intergranular fracture, which was beneficial for the impact toughness of the weld metals.

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Austenite decomposition behavior adjacent to δ-ferrite in a Si-modified Fe-Cr-Ni austenitic stainless steel during thermal aging at 550 °C

Xie,

Chen,

Chen

et al. 2024

Acta Materialia

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Development of New Construction Materials for Innovative Reactor Installation Designs

Cited by 8 publications

References 2 publications

Study of the Mechanisms of Radiation Softening and Swelling upon Irradiation of TiTaNbV Alloys with He2+ Ions with an Energy of 40 keV

Study of the Mechanisms of Radiation Softening and Swelling upon Irradiation of TiTaNbV Alloys with He2+ Ions with an Energy of 40 keV

Effects of Stabilization Heat Treatment on Microstructure and Mechanical Properties of Si-Bearing 15Cr–9Ni–Nb Austenitic Stainless Steel Weld Metal

Austenite decomposition behavior adjacent to δ-ferrite in a Si-modified Fe-Cr-Ni austenitic stainless steel during thermal aging at 550 °C

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