Features of Phase Transformations of Low-activation 12%-Chromium Ferritic-Martensitic Steel Ek-181

Polekhina, N. A.; Litovchenko, I. Yu.; Almaeva, K. V.; Булина, Н. В.; Корчагин, М. А.; Tyumentsev, А. N.; Чернов, В. М.; Leontyeva-Smirnova, M. V.

doi:10.1007/s11182-020-01982-z

Cited by 4 publications

(5 citation statements)

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“…The 9 -12 % Cr ferritic-martensitic steels have been proposed as an alternative to chromium-nickel austenitic steels [1][2][3][4][5][6][7][8][9]. In contrast to austenitic steels, they have a much lower tendency to radiation swelling.…”

Section: Introductionmentioning

confidence: 99%

“…Earlier we showed [8 -10] a possibility of increasing the short-term high-temperature strength of ferritic-martensitic steels by increasing the efficiency of dispersion and substructural strengthening. It was demonstrated that the low-activation ferritic-martensitic steel EK-181 (Fe-12Cr-2W-V-Ta-B) has high short-term strength properties at 650°C and thermal stability of microstructure and mechanical properties under conditions of prolonged (13 500 h.) high-temperature aging at 620°C [9].…”

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: Introductionmentioning

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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“…It is generally considered as the preferred structural material for the test blanket module (TBM) of fusion test reactor in the world. Many countries in the world have carried out a lot of work in the development and characterization of these materials, such as China low-activation martensitic (CLAM) steel produced by Institute of metals, in Shenyang, China [ 5 ], Japan’s F82H [ 6 , 7 ], the European Union’s EUROFER97 [ 8 ] and Rusfer EK-181 [ 9 ]. Due to the complex structure of WCCB blanket and extremely harsh service conditions, the quality of welding and the selection of heat treatment processes play a decisive role in the feasibility and safety of the fusion reactor operation [ 10 ].…”

Section: Introductionmentioning

confidence: 99%

Optimization of Electron Beam Welding Joint of Water-Cooled Ceramic Breeder Blanket

Zhang

Liu

et al. 2021

Materials

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The water-cooled ceramic breeder (WCCB) blanket is a component of the China Fusion Engineering Test Reactor (CFETR). The Reduced Activation Ferrite/Martensite (RAFM) steels are the preferred structural materials for WCCB blanket. As a kind of RAFM steels, China low activation martensitic (CLAM) steel was welded by electron beam welding (EBW), and then quenched-tempered treatment was carried out. The results show that at the welding state, the welding seam was composed of large martensite and δ ferrite and the organization of the heat-affected zone (HAZ) was changed slightly with the different heat input. Moreover, the hardness of welded joints was higher than that of base material (BM), but the impact toughness was very low. After quenched-tempered treatment, the δ ferrite in the weld was eliminated, the residual stress of the test plate decreased as a whole, and the mechanical properties were improved significantly.

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“…Reduced activated ferrite/martensite (RAFM) steels are considered the main candidate material for the structural applications of fusion reactor components, such as the water-cooled ceramic breeder (WCCB) [4,5]. Many countries in the world have done a lot of work in developing and characterizing these materials, such as CLAM in China [6], F82H in Japan [7,8], EUROFER97 in the European Union (EU) [9] and Rusfer EK-181 [10]. Meanwhile, due to the complex structure of the WCCB blanket and extremely harsh service conditions, the quality of the welding plays a decisive role in the feasibility and safety of the fusion reactor operation [11].…”

Section: Introductionmentioning

confidence: 99%

Effect of Pre-Heating and Post-Heating on Electron Beam Welding of Reduced Activation Ferrite/Martensite Steel

Zhang

Liu

et al. 2021

JNE

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Reduced activation ferritic/martensitic (RAFM) steels are considered the main candidate material for the water-cooled ceramic breeder (WCCB) in a fusion reactor. High-energy density welding approaches, such as electron beam welding (EBW) and laser beam welding (LBW), are frequently utilized in the welding of RAFM steels. During the welding process, cracks and other defects are prone to appear. In this paper, EBW was selected for the welding of RAFM steels. Those with and without pre-heat and post-heat treatment by electron beams are studied by finite element simulation and trials. The results show that the experimental results are consistent with the simulation. In particular, in the case of similar deformation, the residual stress after electron beam heat treatment is far less than that without heat treatment. Without heat treatment, the residual stress near the weld is more than 400 MPa, while the residual stress after heat treatment is about 350 MPa. As the reduction of residual stress is essential to prevent the occurrence of cracks and other defects after welding, pre-heat and post-heat treatment by the electron beam is deemed as an effective way to greatly improve the welding quality in RAFM steel welding.

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Features of Phase Transformations of Low-activation 12%-Chromium Ferritic-Martensitic Steel Ek-181

Cited by 4 publications

References 2 publications

New low-activation austenitic steel for nuclear power engineering

New low-activation austenitic steel for nuclear power engineering

Optimization of Electron Beam Welding Joint of Water-Cooled Ceramic Breeder Blanket

Effect of Pre-Heating and Post-Heating on Electron Beam Welding of Reduced Activation Ferrite/Martensite Steel

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