Irradiation-induced microstructural changes, and hardening mechanisms, in model PWR reactor pressure vessel steels

Buswell, J.T.; Phythian, W.J.; McElroy, R.J.; Dumbill, S.; Ray, P.H.N.; Macé, Jean-Reynald; Sinclair, Roger N.

doi:10.1016/0022-3115(95)00026-7

Cited by 142 publications

(60 citation statements)

References 3 publications

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“…Also, significant cosegregation of Ni and Cu, Ni and Si, as well as Mn and Si was observed in the Steel 207N947 (0.1 wt.%Cu) irradiated to 0.018 dpa. This is consistent with published observations of a Ni-Cu effect in irradiation embrittlement [1][2][3][4][5][6]. Odette [14] has suggested that Cu clustering is the necessary and rate controlling process for the nucleation of Mn-Ni rich clusters in model steels.…”

Section: Discussionsupporting

confidence: 92%

“…Numerous empirical studies have been performed to determine the role of various solutes such as Cu, Ni, and P in the irradiation-induced embrittlement of low alloy steels and welds. [1][2][3][4][5][6] This embrittlement is manifested in an increase in the Charpy ductile-to-brittle transition temperatures and a decrease in the Charpy upper shelf energy of the steel, and is associated with an increase in hardness of the material. These irradiation-induced changes in mechanical properties of low alloy steels have been associated with subtle, ultra-fine-scale changes in the microstructure, such as the formation of diffuse solute-enriched "clusters" or "precipitates", which have been identified by atom probe field-ion microscopy [7,8].…”

Section: Introductionmentioning

confidence: 99%

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Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects

Burke¹,

Stofanak²,

Hyde

et al. 2004

Effects of Radiation on Materials: 21st International Symposium

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Neutron irradiation can promote significant changes in the microstructure and associated mechanical properties of low alloy steels. In particular, irradiation can induce the formation of non-equilibrium phases and segregation, which may lead to a degradation in toughness. In this study, the microstructural changes caused by neutron irradiation have been characterized in A508 Grade (Gr) 4N-type steels (~3.5% Ni) using a variety of state-of-the-art analytical techniques including 3D-Atom Probe Field-Ion Microscopy and Small Angle Neutron Scattering, along with post-irradiation annealing studies combining Positron Annihilation Lineshape Analysis and hardness measurements. Important differences between conventional and "superclean" A508 Gr 4N steel have been identified in this investigation. The data indicate that Ni is not the controlling factor in the irradiation damage behavior of these materials; rather, the Mn content of the steel is a dominant factor in the irradiation-induced microstructural development of soluterelated hardening features.

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Section: Discussionsupporting

confidence: 92%

Section: Introductionmentioning

confidence: 99%

Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects

Burke¹,

Stofanak²,

Hyde

et al. 2004

Effects of Radiation on Materials: 21st International Symposium

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“…1 The point defects created by the neutron induced cascades are responsible for the diffusion of the solute atoms, leading to the formation of solute rich precipitates within the matrix. These clusters are enriched in Cu, Ni, Mn, Si, and P. 2,3 The presence of solute atoms also influences the formation of point defect clusters. Both the change in point defect clusters and the formation of solute rich clusters influence the mechanical properties of the steels.…”

Section: Introductionmentioning

confidence: 99%

Ab initiostudy of solute transition-metal interactions with point defects in bcc Fe

Olsson

Klaver²,

Domain³

2010

Phys. Rev. B

205

150

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The properties of 3d, 4d, and 5d transition-metal elements in ␣-Fe have been studied using ab initio density-functional theory. The intrinsic properties of the solutes have been characterized as well as their interaction with point defects. Vacancies and interstitials of ͗110͘ and ͗111͘ orientations have been considered in order to discern trends that may explain experimental evidence of solute influences on radiation response and possibly aid future material design regarding the choice of alloy composition. Depending on the solute element, the different interactions are governed by the chemical interactions and the solute size factor. It is shown that magnetic interactions play an important role for the properties of the center series 3d elements, especially so for the antiferromagnetically coupling V, Cr, and Mn. For the 4d, 5d, and remaining 3d elements the interaction with point defects is mainly governed by the solute size factor. The solute-solute interaction is mostly repulsive with a few exceptions. The interactions with vacancies are in most cases binding; but the second nearest neighbor configurations exhibit strong repulsion for the early transition metals. Cr and Mn interact strongly binding with interstitial defects. The trends of the solute defect interactions have been determined to depend on the characteristic local deformation. Early transition metals interact stronger with defects than late ones of equal size factor.

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“…The formation of these different types of precipitates may be at least partly radiation-induced, but no consensus exists about their actual origin, nature and mechanism of formation. There is, however, consensus about the fact that the interaction of these nano-defects with dislocations is the main cause of hardening and embrittlement of these steels [7][8][9][10][11][12][13][14][15][16]. In this framework, large scale atomistic simulations in multi-component alloys are of fundamental importance with a view to cast some light on the mechanisms leading to the formation of the mentioned different classes of precipitates, as well as in order to study in detail their interaction with dislocations as source of hardening.…”

Section: Introductionmentioning

confidence: 99%

Ternary Fe–Cu–Ni many-body potential to model reactor pressure vessel steels: First validation by simulated thermal annealing

Bonny

Pasianot

Castin

et al. 2009

Philosophical Magazine

251

110

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In recent years the development of atomistic models dealing with microstructure evolution and subsequent mechanical property change in reactor pressure vessel steels has been recognised as an important complement to experiments. In this framework, a literature study has shown the necessity of many-body interatomic potentials for multi-component alloys. In this paper we develop a ternary many-body Fe-Cu-Ni potential for this purpose. As a first validation, we used it to perform a simulated thermal annealing study of the Fe-Cu and FeCu-Ni alloys. Good qualitative agreement with experiments is found, although fully quantitative comparison proved impossible, due to limitations in the used simulation techniques. These limitations are also briefly discussed here.

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Irradiation-induced microstructural changes, and hardening mechanisms, in model PWR reactor pressure vessel steels

Cited by 142 publications

References 3 publications

Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects

Microstructural Aspects of Irradiation Damage in A508 Gr 4N Forging Steel: Composition and Flux Effects

Ab initiostudy of solute transition-metal interactions with point defects in bcc Fe

Ternary Fe–Cu–Ni many-body potential to model reactor pressure vessel steels: First validation by simulated thermal annealing

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