Mechanical properties and microstructure of three Russian ferritic/martensitic steels irradiated in BN-350 reactor to 50dpa at 490°C

Dvoriashin, A. M.; Porollo, S. I.; Konobeev, Yu. V.; Budylkin, N. I.; Mironova, E. G.; Ioltukhovskiy, A.G.; Leontyeva-Smirnova, M. V.; Garner, F.A.

doi:10.1016/j.jnucmat.2007.03.161

Cited by 20 publications

(7 citation statements)

References 4 publications

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“…Lim and his colleagues also developed Al 2 O 3forming FeCrAl ferritic steels [18,19]. Both Si-containing ferritic/martensitic steels and Alcontaining ferritic steels may exhibit significant radiation embrittlement due to the segregation of Si/Al to grain boundaries and the formation of a Cr-rich α'-phase at temperatures of 300-500 • C [20][21][22]. To achieve corrosion resistance while preserving desirable mechanical properties, a hybrid fuel cladding tube has been suggested by Ballinger and his colleagues in the case of Si-containing alloys on radiation-resistant ferritic/martensitic steels [23].…”

Section: Introductionmentioning

confidence: 99%

High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application

et al. 2021

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The corrosion of nuclear-grade steels in lead–bismuth eutectic (LBE) complicates the realization of high coolant temperatures. Corrosion tests of T91, HT9, and SS316L were performed in static cells at 600 °C for 2000 h at an oxygen level of 10−6 wt.%. The obtained corrosion surfaces of post-processed samples were characterized by several microscopy methods. Up to 1000 h, all the alloys exhibited an evolution of duplex oxide layers, which were spalled until 2000 h due to their increased thickness and decreased integrity. Following the spallation, a thin internal Cr-rich oxide layer was formed above the Cr-depleted zone for T91 and HT9. SS316L was penetrated by LBE down to 300 μm in severe cases. A comparison on the corrosion depths of the materials with regard to the parabolic oxidation law with abundant literature data suggests that it may lose its validity once the duplex layer is destroyed as it allows LBE to penetrate the metal substrate.

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Section: Introductionmentioning

confidence: 99%

High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application

et al. 2021

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“…The precipitation of γ-hydride in zirconium generates three possible equivalent orientation variants with an angle of 120°between each other. The non-zero components of the stressfree transformation strain tensor for the hydride formation are along [0 0 0 1], [11][12][13][14][15][16][17][18][19][20], and directions, respectively. In the simulations, the interfacial energy was assumed to be isotropic.…”

Section: Simulations Of Different Phenomena In Radiation-induced Micrmentioning

confidence: 99%

“…9,[18][19][20][21] The radiation-induced heterogeneity of the microstructures depends on the initial phase and defect structure of the fresh (non-irradiated) materials and on the type and severity of the radiation environment. Fundamental understanding of heterogeneous three-dimensional microstructure evolution is crucial to the development of advanced radiation tolerant materials that can significantly improve the life extension of current reactor fleet and impact advanced reactor designs.…”

Section: Introductionmentioning

confidence: 99%

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials

Sun

et al. 2017

npj Comput Mater

127

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Complex microstructure changes occur in nuclear fuel and structural materials due to the extreme environments of intense irradiation and high temperature. This paper evaluates the role of the phase field method in predicting the microstructure evolution of irradiated nuclear materials and the impact on their mechanical, thermal, and magnetic properties. The paper starts with an overview of the important physical mechanisms of defect evolution and the significant gaps in simulating microstructure evolution in irradiated nuclear materials. Then, the phase field method is introduced as a powerful and predictive tool and its applications to microstructure and property evolution in irradiated nuclear materials are reviewed. The review shows that (1) Phase field models can correctly describe important phenomena such as spatial-dependent generation, migration, and recombination of defects, radiation-induced dissolution, the Soret effect, strong interfacial energy anisotropy, and elastic interaction; (2) The phase field method can qualitatively and quantitatively simulate two-dimensional and three-dimensional microstructure evolution, including radiation-induced segregation, second phase nucleation, void migration, void and gas bubble superlattice formation, interstitial loop evolution, hydrate formation, and grain growth, and (3) The Phase field method correctly predicts the relationships between microstructures and properties. The final section is dedicated to a discussion of the strengths and limitations of the phase field method, as applied to irradiation effects in nuclear materials. npj Computational Materials (2017) 3:16 ; doi:10.1038/s41524-017-0018-y INTRODUCTIONHigh energy particle (such as neutron, ion, and electron) radiation can create major changes in the shape and thermo-mechanical properties of nuclear fuels and structural components of nuclear reactors. These changes are caused by radiation-induced evolution of compositions and microstructures. The main effects of radiation on reactor materials are: (1) dimensional change associated with gas bubble swelling, void swelling, grain growth, and creep; 1-5 (2) loss of ductility and increase in ductile-brittle transition temperature (DBTT) due to the formation of secondphase precipitates, self-interstitial atomic (SIA) loops, and dislocation networks; 6, 7 (3) oxidation and corrosion accelerated by high temperature, fission products, and radiation damage; 8-10 and (4) local and bulk changes in chemical composition, including irradiation-enhanced segregation of alloy components and phase separation.11-17 Figure 1 shows typical microstructures observed in irradiated materials.9, 18-21 The radiation-induced heterogeneity of the microstructures depends on the initial phase and defect structure of the fresh (non-irradiated) materials and on the type and severity of the radiation environment. Fundamental understanding of heterogeneous three-dimensional microstructure evolution is crucial to the development of advanced radiation tolerant materials that can significa...

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“…However, Alcontaining ferritic steels show significant radiation embrittlement as a result of Al segregation to grain boundaries and Cr-rich a 0 phase formation at the temperature range of 300e500 C (Dvoriashin et al, 2007). To achieve appropriate corrosion resistance while keeping desirable mechanical properties, the hybrid fuel cladding tube, HT-9 or T-91 overlaid with Al-containing ferritic steels, was selected .…”

Section: Fuel Rod Designmentioning

confidence: 99%

Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation

Shin

Choi

Cho

et al. 2015

Progress in Nuclear Energy

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Mechanical properties and microstructure of three Russian ferritic/martensitic steels irradiated in BN-350 reactor to 50dpa at 490°C

Cited by 20 publications

References 4 publications

High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application

High-Temperature Corrosion Behaviors of Structural Materials for Lead-Alloy-Cooled Fast Reactor Application

A review: applications of the phase field method in predicting microstructure and property evolution of irradiated nuclear materials

Advanced passive design of small modular reactor cooled by heavy liquid metal natural circulation

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