Radiation creep and phase instability of low-activation austenitic steel 12 Cr-20 Mn-W under neutron irradiation in the FFTF fast reactor

Demina, E. V.; Ivanov, L.I.; Platov, Yu. V.; Prusakova, M. D.; Eikholtser, S. R.; Tolochko, M. B.; Garner, F.А.

doi:10.1134/s207511331105011x

Cited by 5 publications

(17 citation statements)

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“…The weight of the experimental ingot is 2.5 kg. A significant difference from the previously studied compositions [5,[11][12][13][14][15] is a higher content of manganese and an increased content of strong carbide-forming elements (with a high tendency to carbide formation): Ta, Ti, V, Zr, W. In accordance with the concept of low-activation materials, the content of such highly activated elements as Ni, Cu, Nb, Mo, Co, Al in the new steel, also N and O is reduced to the minimum level.…”

Section: Materials and Experimental Methodsmentioning

confidence: 67%

“…3 this case, similarly to the numerous dispersion strengthened steels, nanosized particles pin the dislocation substructure. In the process of TEM studies, no bcc phase (α-ferrite), σ-phase, or carbides of the M 23 C 6 type, which can be formed in chromium-manganese austenitic steels [11,12], were found. Element mapping of the region near one of the dispersed particles is shown in Fig.…”

Section: Resultsmentioning

confidence: 99%

“…Despite the fact that new low-activation alloys and steels have been developed by now and are being actively investigated, higher operating temperatures and degrees of the nuclear fuel burnout and a planned reduction in the environmental load from the nuclear waste structural materials necessitate the search for new compositions and the development of new alloys that would meet these conditions. The design of new low-activation austenitic steels as a new research avenue was initiated in [5,11,12] -Russia, [13] -USA and [14,15] -Japan in the 90s of the XX century and in early 2000s. In these works on the Fe-12Cr-(20 -25) Mn alloys, it is shown that such steels with a carbon content of 0.1-0.25 wt.% have an austenitic structure with coarse particles of M 23 C 6 carbides along the grain boundaries and MC particles in the grain interior.…”

Section: Introductionmentioning

confidence: 99%

“…Despite the high interest in low-activation austenitic steels and a significant number of relevant publications within the above-mentioned period [5,[11][12][13][14][15], the research of low-activation ferritic-martensitic steels has become even more extensive [1][2][3][4][5][6][7][8][9]. In recent years, there have been only few publications on the study of microstructure, mechanical and corrosion properties of low-activation austenitic steels [16,17].…”

Section: Introductionmentioning

confidence: 99%

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New low-activation austenitic steel for nuclear power engineering

et al. 2022

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Vacuum induction melting is used to fabricate a new low-activation chromium-manganese austenitic steel with an increased, compared to well-known analogues, manganese content and additional alloying with strong carbide-forming elements (with a high tendency to carbide formation). Using the methods of transmission and scanning electron microscopy, the features of its microstructure, elemental and phase compositions in the solution treated state are studied. It is shown that the steel has an austenitic structure with a grain size of tens of micrometers. Its dislocation substructure is represented by flat dislocation pileups, which is typical for materials with low stacking fault energy. Coarse (submicron) particles of MC carbides (M = Ti, Ta, Zr, W) are found along the boundaries and inside the grains. Nanosized particles of the MC type fix the grain and subgrain boundaries and the dislocation substructure of the steel. Mechanical tensile tests are carried out at room and elevated temperatures. It is shown that the new steel has higher yield and tensile strength values, as well as elongation to failure compared to the austenitic chromiumnickel steels currently used in nuclear power engineering and well-known chromium-manganese low-activation steels.

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Section: Materials and Experimental Methodsmentioning

confidence: 67%

Section: Resultsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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New low-activation austenitic steel for nuclear power engineering

et al. 2022

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“…[2][3] Austenitic stainless steel containing nickel and Inconel alloys face a large numbers of problems such as He-embritllement and long lived nuclides as a waste material. [4][5] Hence, the alloys containing nickel should be minimized or eliminated from the reactor core. In this regard, low activation austenitic manganese-nitrogen stainless steels have raised interest as an alternative to austenitic nickel stainless steels and Inconel alloys.…”

Section: Introductionmentioning

confidence: 99%

Low Activation-Modified High Manganese-Nitrogen Austenitic Stainless Steel for Fast Reactor Pressure Vessel Cladding

Saeed¹

2018

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Low and free nickel austenitic stainless steel alloys were developed successfully and proposed to be used as a liquid sodium coolant fast reactor pressure vessel cladding. A standard austenitic stainless steel SS316L (AISI 316L) was produced as a reference sample. The nickel content was partially or totally replaced by manganese and nitrogen. The microstructure of the produced stainless steel alloys was investigated using Schaeffler diagram, optical microscopy and X-ray diffraction patterns (XRD). Mechanical properties of the developed stainless steel grads were investigated using Vickers hardness, impact and tensile tests at room temperature. Sodium chloride was used to study the corrosion rate of the investigated alloys by open circuit potential technique. Slow and total slow neutrons removal cross sections were measured using 241 Am-Be neutron source and highly calibrated He-3 detector. Eight gamma ray lines which emitted from 60 Co and 232 Th radioactive sources and HPGe detector were used to study the attenuation parameters of the produced alloys. Metallography, Schaeffler diagram and XRD results showed that all the produced stainless steels are mainly of austenite phase with a small ferrite phase. The developed manganese-nitrogen stainless steels showed higher hardness, yield and ultimate tensile strength than SS316L. The elongation of developed stainless steels is relatively lower than the standard SS316L. The impact toughness was reduced with replacement of Ni by Mn. The developed manganese stainless steels have a higher total slow removal cross section than SS316L. On the other hand, the slow neutron and gamma rays have nearly the same behavior for all studied stainless steels.

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