Effects of thermal sensitization on radiation-induced segregation in type 304 stainless steel irradiated with He-ions

Okada, Osami; Nakata, Kiyotomo; Kasahara, Shigeki

doi:10.1016/s0022-3115(98)00733-8

Cited by 18 publications

(6 citation statements)

References 14 publications

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“…Additionally, grain growth in the HAZ can occur due to high temperatures during welding (Katundi et al, 2010). These aspects tend to modify the mechanical properties and corrosion resistance of the welded joints (Okada et al, 1999;Bayraktar et al, 2011;Niekerk and Toit, 2011;Lakshminarayanan and Balasubramanian, 2012).…”

Section: Introductionmentioning

confidence: 99%

Heat input effect on the microstructural transformation and mechanical properties in GTAW welds of a 409L ferritic stainless steel

et al. 2016

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Welds without filler metal and welds using a conventional austenitic stainless steel filler metal (ER308L) were performed to join a ferritic stainless steel with Gas Tungsten Arc Welding process (GTAW). Welding parameters were adjusted to obtain three different heat input values. Microstructure reveals the presence of coarse ferritic matrix and martensite laths in the Heat Affected Zone (HAZ). Dilution between filler and base metal was correlated with the presence of austenite, martensite and ferrite in the weld metal. Weld thermal cycles were measured to correlate the microstructural transformation in the HAZ. Microhardness measurements (maps and profiles) allow to identify the different zones of the welded joints (weld metal, HAZ, and base metal). Comparing the base metal with the weld metal and the HAZ, a hardness increment (~172 HV 0.5 to ~350 HV 0.5 and ~310 HV 0.5 , respectively) was observed, which has been attributed to the martensite formation. Tensile strength of the welded joints without filler metal increased moderately with respect to base metal. In contrast, ductility was approximately 25% higher than base metal, which provided a toughness improvement of the welded joints. RESUMEN:Efecto del calor de aporte sobre la transformación microestructural y las propiedades mecánicas en soldadura GTAW de un acero inoxidable ferrítico 409L. Se llevaron a cabo soldaduras sin material de aporte y empleando un electrodo convencional (ER308L) para unir un acero inoxidable ferrítico, empleando el proceso de soldadura de arco con electrodo de tungsteno (GTAW). Los parámetros de soldadura fueron ajustados para obtener tres valores diferentes de calor de aporte. La microestructura revela la presencia de una matriz ferrítica gruesa y placas de martensita en la Zona Afectada por el Calor (ZAC). La dilución entre el metal base y de aporte fue correlacionada con la presencia de austenita, martensita y ferrita en el metal de soldadura. Los ciclos térmicos de la soldadura fueron medidos para correlacionar la transformación microestrutural en la ZAC. Mediciones de microdureza (mapas y perfiles), permitieron identificar las diferentes zonas de las uniones soldadas (metal base, ZAC y metal de soldadura). Se observó un incremento de dureza en el metal de soldadura (~350 HV 0,5 ) y en la ZAC (~310 HV 0,5 ), en relación al metal base (~172 HV 0,5 ), que se ha atribuido a la formación de martensita. La resistencia a la tensión de las uniones soldadas sin metal de aporte aumentó ligeramente con respecto al metal base. En cambio, la ductilidad se incrementó aproximadamente un 25% en relación al material base, lo cual mejoró la tenacidad de las uniones.

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Section: Introductionmentioning

confidence: 99%

Heat input effect on the microstructural transformation and mechanical properties in GTAW welds of a 409L ferritic stainless steel

et al. 2016

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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%

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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“…The noble-gas ion implantation method has been used to study the effects of particle irradiation on metals [1][2][3][4][5][6][7][8] and ceramics [9][10][11][12][13][14]. Various noble-gases such as He [3,5], Ar [7], Ne [4,7,12], Kr [8,13], and Xe [1,2,6,7,[9][10][11][12] have been used as sources of implantation ions.…”

Section: Introductionmentioning

confidence: 99%

“…Various noble-gases such as He [3,5], Ar [7], Ne [4,7,12], Kr [8,13], and Xe [1,2,6,7,[9][10][11][12] have been used as sources of implantation ions. Among them, the heavy noble-gases such as Kr and Xe have so large atomic sizes that can generate displacement damage in the matrix during the implantation and the substitutional sites or voids of lattice can be used for the diffusion of these ions in the matrix.…”

Section: Introductionmentioning

confidence: 99%

Precipitation behavior of Xe at grain boundaries in Si3N4 ceramic during implantation at elevated temperature

Heo

Takeguchi²,

Mitsuishi³

et al. 2010

Journal of Nuclear Materials

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Effects of thermal sensitization on radiation-induced segregation in type 304 stainless steel irradiated with He-ions

Cited by 18 publications

References 14 publications

Heat input effect on the microstructural transformation and mechanical properties in GTAW welds of a 409L ferritic stainless steel

Heat input effect on the microstructural transformation and mechanical properties in GTAW welds of a 409L ferritic stainless steel

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

Precipitation behavior of Xe at grain boundaries in Si3N4 ceramic during implantation at elevated temperature

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