Multiscale modelling in nuclear ferritic steels: From nano-sized defects to embrittlement

Castin, N.; Bonny, G.; Konstantinović, M.J.; Bakaev, A.; Bergner, F.; C., Courilleau,; Domain, Christophe; Gómez-Ferrer, B.; Hyde, J.M.; Messina, Luca; Monnet, Ghiath; Pascuet, M.I.; Radiguet, B.; Serrano, Marta; Malerba, Lorenzo

doi:10.1016/j.mtphys.2022.100802

Cited by 5 publications

(4 citation statements)

References 65 publications

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“…In consequence current embrittlement trend curves will not incorporate any influence from the predicted acceleration. (The absence of a high-fluence increase in the embrittlement rate within the PLOTTER data is also supported by the multiscale modelling shown in (Castin et al, 2022) which successfully predicts the behaviour of the low-Cu steels within PLOTTER via a model which does not allow for precipitation. )…”

Section: Flux Effects On Grain Boundary Segregation and Non-hardening...mentioning

confidence: 53%

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The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

Ortner,

Styman,

Long

2024

Front. Nucl. Eng.

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It is necessary to quantify the effects of flux on reactor pressure vessel steel embrittlement under neutron irradiation, if surveillance or high-flux test reactor data is used to predict vessel embrittlement occurring at lower fluxes. This is particularly important when considering embrittlement occurring during extended (60–80 years) operation for which there is no direct experience. Dedicated investigations are time-consuming and expensive even when only small flux-fluence ranges are investigated, so collating data from multiple campaigns is necessary to provide sufficient information to cover the wide range of fluxes required for vessel assessment in the long term. This paper collates and reviews such data. The review finds that flux dependences probably differ in sign and strength in different regimes (low flux and fluence, intermediate flux at low and high fluence, high flux at low and high fluence) with the regime limits affected by composition and temperature. The current understanding of diffusion processes and microstructural development are invaluable in interpreting the trends and limits. Many contradictory data sets were found, however, and not all contradictions could be dismissed as resulting from poor quality data. Suggestions are made for investigations to clarify the uncertainties. One wide-ranging model of flux effects, based on an extensive data set, is used to compare high-fluence data from different sources, to assess whether embrittlement rates accelerate after a high, threshold fluence. The model helps to identify experiments which investigated comparable flux-fluence-temperature regimes. The comparable data are split evenly between data sets supporting acceleration after a particular fluence and data sets contradicting it. The model identifies regimes in which further campaigns would clarify the causes of these contrasting observations.

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Section: Flux Effects On Grain Boundary Segregation and Non-hardening...mentioning

confidence: 53%

“…FIGURE 11High fluence data from 15Kh2MFA CrMoV WWER steel and A533B plate (JRQ) irradiated at 270 °C and fluxes between 1011 and 1012 n.cm −2 s −1(Castin et al, 2022) 3 .…”

mentioning

confidence: 99%

The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

Ortner,

Styman,

Long

2024

Front. Nucl. Eng.

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“…Is it an irradiation-enhanced process dictated by thermodynamics or an irradiation-induced process that would not occur without irradiation? Current models of radiation-induced precipitate formation are described and are based on two major conflicting theories of NSM precipitate formation and growth [1,[36][37][38][39].…”

Section: High-cu Materialsmentioning

confidence: 99%

“…In [39], a model of NiMnSiPCu-enriched cluster formation under irradiation was developed using the Objected Kinetic Monte Carlo OKMC method, which allows predicting the values of number density, size, and volume fraction for solute clusters with regard to the chemical composition (Ni, Mn, Si, P, and Cu content in at.%), irradiation conditions (temperature and flux) and cumulative dose (irradiation time equivalent with due regard to the flux). Cr atoms, present in significant amounts in VVER steels, are taken into account through the impact on the diffusion coefficient of self-interstitial defects.…”

Section: High-cu Materialsmentioning

confidence: 99%

The Effect of Operational Factors on Phase Formation Patterns in the Light-Water Reactor Pressure Vessel Steels

Fedotova,

Kuleshova

2023

Metals

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This paper presents the results of atom probe tomography studies on radiation-induced phase formation in light-water reactor pressure vessel steels after neutron irradiation under various conditions in comparison with the literature data. The given irradiation conditions are fluence (10–100) × 1022 m−2, flux (5–2700) × 1014 m−2s−1 and irradiation temperature (50–400) °C. The composition of the studied steels varies in a wide range for the elements significantly affecting radiation and thermal resistance of steels: Ni in the range of 0.2–6.0 wt.%, Mn–0.03–1.1 wt.%, Cu–0.01–0.16 wt.%, and P–0.01–0.03 wt.%. The number density, volume fraction, size, composition, and nucleation sites of precipitates are determined. The regularities of the effect of various operational factors on the phase formation in these steels have been analyzed and revealed. The study shows that in materials with high copper content, Cu-rich precipitates are formed by a radiation-enhanced mechanism. In materials with low copper content, their formation upon irradiation at 300 °C occurs by a radiation-induced mechanism since the main nucleation sites are point defect clusters formed in cascades. At the same time, the density, volume fraction, and composition of the precipitates depend on the steel composition (Ni and Mn content). In the steel with increased Ni content up to 5 wt.% but with ultra-low Mn content ≤ 0.03 wt.%, it is possible to suppress the formation of Ni-Si-Mn precipitates under irradiation.

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How precisely are solute clusters in RPV steels characterized by atom probe experiments?

Castin,

Klupś,

Konstantinović

et al. 2025

Journal of Nuclear Materials

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Multiscale modelling in nuclear ferritic steels: From nano-sized defects to embrittlement

Cited by 5 publications

References 65 publications

The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

The Effect of Operational Factors on Phase Formation Patterns in the Light-Water Reactor Pressure Vessel Steels

How precisely are solute clusters in RPV steels characterized by atom probe experiments?

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