Metallurgical properties of reduced activation martensitic steel Eurofer’97 in the as-received condition and after thermal ageing

Fernández, P.; Lancha, A.M.; Lapeña, J.; Serrano, Marta; Hernández‐Mayoral, M.

doi:10.1016/s0022-3115(02)01013-9

Cited by 86 publications

(40 citation statements)

References 4 publications

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“…After thermal ageing at 500°C/5 000 h and 600°C/1 000 h no significant changes in composition were observed, although MX particles did exhibit a slight growth. 12) MX particles Ta or V-rich were also reported for normalized ORNL RA steels, tempered at 750°C. 7) These three types of morphologies, including in some cases the "wing" morphology, have been observed in 9CrMoVNb, 13) 9CrWCoVNb 14) and CrWNb 15) steels after tempering but, to our knowledge, the "wing" morphology involving Ta and V has not been reported in other alloys of composition similar to Eurofer97, such as F82H or JLF1.…”

Section: Morphology and Compositionmentioning

confidence: 85%

“…7) Similar results for carbide composition measurements were found in experimental AEA-Culham 9 to 11CrWVTa steels after tempering at 675 or 750°C and ageing at 750°C for 500 h or at 500°C for 1 000 h, 18) and for the Eurofer97 RA alloy after tempering 11) and ageing. 12) On the other hand, M 7 C 3 , M 23 C 6 , M 3 C, and M 6 C carbides have been observed in 2.25Cr steels. 7) Ta uptake by the M 23 C 6 phase is controversial.…”

Section: C 6 M 7 C 3 or M 6 C Carbidesmentioning

confidence: 97%

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Thermodynamic Modeling in Reduced Activation Steels

Danón

Servant

2005

ISIJ Int.

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Reduced Activation (RA) martensitic steels of the 9/11CrWVTa type are promising candidates for fusion reactor applications as long as they exhibit good mechanical properties-similar to those of commercial martensitic steels of the 9/12CrMo(NbV) type-and satisfy design criteria related to the behavior under irradiation. A contribution on thermodynamic modeling in RA steels is presented. The current status of the development of a thermodynamic database in the framework of the CALPHAD approach is reported. Thermodynamic calculations concerning RA alloys are discussed which can be helpful to interpret experimental observations on phase relationships, phase compositions, transition temperatures, etc.

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Section: Morphology and Compositionmentioning

confidence: 85%

Section: C 6 M 7 C 3 or M 6 C Carbidesmentioning

confidence: 97%

Thermodynamic Modeling in Reduced Activation Steels

Danón

Servant

2005

ISIJ Int.

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“…The shear modulus of steel is µ = 80 GPa, ν = 0.29. For comparison, the yield strength of Eurofer97 ferritic-martensitic steel is 530 MPa [68]. of radiation-induced stresses can be estimated by evaluating the product of the shear modulus of the material and function ω rel (r), suitably averaged over the volume of the component.…”

Section: Strains Stresses and Swelling In A Spherical Shell: An Exacmentioning

confidence: 99%

A multi-scale model for stresses, strains and swelling of reactor components under irradiation

et al. 2018

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Predicting strains, stresses and swelling in nuclear power plant components exposed to irradiation directly from the observed or computed defect and dislocation microstructure is a fundamental problem of fusion power plant design that has so far eluded a practical solution. We develop a model, free from parameters not accessible to direct evaluation or observation, that is able to provide estimates for irradiation-induced stresses and strains on a macroscopic scale, using information about the distribution of radiation defects produced by high-energy neutrons in the microstructure of materials. The model exploits the fact that elasticity equations involve no characteristic spatial scale, and hence admit a mathematical treatment that is an extension to that developed for the evaluation of elastic fields of defects on the nanoscale. In the analysis given below we use, as input, the radiation defect structure data derived from ab initio density functional calculations and large-scale molecular dynamics simulations of high-energy collision cascades. We show that strains, stresses and swelling can be evaluated using either integral equations, where the source function is given by the density of relaxation volumes of defects, or they can be computed from heterogeneous partial differential equations for the components of the stress tensor, where the density of body forces is proportional to the gradient of the density of relaxation volumes of defects. We perform a case study where strains and stresses are evaluated analytically and exactly, and develop a general finite element method implementation of the method, applicable to a broad range of predictive simulations of strains and stresses induced by irradiation in materials and components of any geometry in fission or fusion nuclear power plants.

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“…Among the important problems limiting the lifetime of the core components, the void-swelling, loss of creep resistance and transmutation-induced radioactive elements are the major concern. Towards mitigating these problems, martensitic/ferritic steels are considered as candidate materials [1][2][3][4][5][6]. Although the conventional 9Cr-1Mo ferritic/martensitic steels have excellent void swelling resistance, it is necessary to modify them by replacing elements like Molybdenum and Niobium with Tungsten and Tantalum respectively to reduce the activation problems.…”

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confidence: 99%

Positron annihilation studies on 9Cr reduced activation ferritic/martensitic steels

Ragunanthan

Babu

Chirayath

et al. 2009

Phys. Status Solidi (c)

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Positron annihilation, microstructural and hardness studies were carried out in a 9Cr reduced activation ferrtic ‐ martensitic steel (9%Cr‐1%W‐0.1%C) subjected to isochronal annealing in the temperature range of 300 to 1273 K. The measured lifetime in the ‘as‐received’ (normalized and tempered) condition was 147 ps, which exhibited considerable reduction around 670 K, indicating the annealing out of small vacancy‐defects in the matrix or matrix‐precipitate interfaces. The observed positron lifetime exhibited a broad maximum between 670 K and 1070 K, indicating the existence of second annealing stage. Between 1070 K and 1270 K, a sharp maxium is exhibited in lifetime as third annealing stage. Doppler S‐parameter has also exhibited similar annealing stages. Ab‐intio positron lifetime calculations for various defect‐impurity cluster configurations in ferritic‐matrix based Fe system are reported to understand the experimental results. (© 2009 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)

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Metallurgical properties of reduced activation martensitic steel Eurofer’97 in the as-received condition and after thermal ageing

Cited by 86 publications

References 4 publications

Thermodynamic Modeling in Reduced Activation Steels

Thermodynamic Modeling in Reduced Activation Steels

A multi-scale model for stresses, strains and swelling of reactor components under irradiation

Positron annihilation studies on 9Cr reduced activation ferritic/martensitic steels

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