PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen plant lifetime

Mazouzi, A. Al; Alamo, A.; Lidbury, David; Moinereau, Dominique; Dyck, S. Van

doi:10.1016/j.nucengdes.2011.01.054

Cited by 21 publications

(11 citation statements)

References 41 publications

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“…It consists of modeling, for example, damage production processes by molecular dynamics calculations, diffusion processes by ab initio calculations, clustering processes by kinetic Monte Carlo calculations, dislocation interactions by dislocation dynamics calculations, and macroscopic deformation and fracture processes by crystalline plasticity calculations. In European countries, a multiscale approach was organized as the PERFECT project and has been followed by the PERFORM60 project [171][172][173]. The major results of the PERFECT project were summarized in a special publication [174].…”

Section: Multiscale Modelingmentioning

confidence: 99%

Current understanding of radiation-induced degradation in light water reactor structural materials

Fukuya¹

2013

Journal of Nuclear Science and Technology

161

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Current phenomenological knowledge and understanding of mechanisms are reviewed for radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted stress corrosion cracking of core internals of stainless steels. Accumulated test data of irradiated materials in light water reactors and microscopic analyses by using state-of-the-art techniques such as a three-dimensional atom probe and electron backscatter diffraction have significantly increased knowledge about microstructural features. Characteristics of solute clusters and deformation microstructures and their contributions to macroscopic material property changes have been clarified to a large extent, which provide keys to understand in the degradation mechanisms. However, there are still fundamental research issues that merit study for long-term operation of reactors that requires reliable quantitative prediction of radiation-induced degradation of component materials in low-dose rate high-dose conditions.

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Section: Multiscale Modelingmentioning

confidence: 99%

Current understanding of radiation-induced degradation in light water reactor structural materials

Fukuya¹

2013

Journal of Nuclear Science and Technology

161

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“…The long-term operation of existing NPPs has already been accepted in many countries as a strategic objective to ensure adequate supply of electricity over the coming decades. Operating conditions that affect the design lifetime include neutron exposure (fluence), as well as the number and magnitude of temperature and/or pressure cycles in both normal conditions and hypothetical accidental conditions [2,3]. License renewal and periodic safety reviews (PSRs) are the two basic regulatory approaches that are required for an authorization of the long-term operation of NPPs [1].…”

Section: Introductionmentioning

confidence: 99%

Magnetic Investigation of Cladded Nuclear Reactor Blocks

et al. 2022

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The wall, made of ferromagnetic steel, of a nuclear reactor pressure vessel is covered by an austenitic (very weakly ferromagnetic) cladding. In this work, we investigated how the base material and the cladding can be inspected separately from each other by nondestructive magnetic measurements. It was found that with the proper choice of the magnetizing yoke, these two different materials could be measured independently of each other. The effect of the yoke’s size was studied by the numerical simulation of magnetic flux, pumped into the material during magnetic measurements. Measurements were performed by two different sizes of yokes on pure base material, on base material under cladding and on cladding itself. Experiments verified the results of the simulation. Our results can help for the future practical application of magnetic methods in the regular inspection of nuclear power plants.

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“…The data to which these correlations are fit come from vessel surveillance [3], decommissioned vessels [4], or irradiation campaigns in materials testing reactors (MTR) [5][6][7]. For a longer-term application, effort has been put to develop fully physically informed suites of computer simulation codes, aimed at predicting RPV steel radiation hardening [8,9], including microstructural examination studies in support of modelling [10][11][12][13][14][15][16][17][18][19][20][21][22][23][24][25][26][27][28]. These studies revealed that radiation hardening in RPV steels, as well as in other types of iron alloys such as high-Cr ferritic-martensitic (F-M) materials, is mainly the consequence of the formation of high densities (~10 23 m -3 ) of nanometre-size solute-rich clusters (NSRC), which act as obstacles to dislocation motion [29,30].…”

Section: Introductionmentioning

confidence: 99%

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

et al. 2019

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The formation of nano-sized, coherent, solute-rich clusters (NSRC) is known to be an important factor degrading the macroscopic properties of steels under irradiation. The mechanisms driving their formation are still debated. This work focuses on low-Cu reactor pressure vessel (RPV) steels, where solute species are generally not expected to precipitate. We rationalize the processes taking place at the nanometre scale under irradiation, relying on the latest theoretical and experimental evidence on atomic-level diffusion and transport processes. These are compiled in a new model, based on the object kinetic Monte Carlo (OKMC) technique. We evaluate the relevance of the underlying physical assumptions by applying the model to a large variety of irradiation experiments. Our model predictions are compared with new experimental data obtained with atom probe tomography and small angle neutron scattering, complemented with information from the literature. The results of this study reveal that the role of immobilized selfinterstitial atoms (SIA) loops dominates the nucleation process of NSRC.

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PERFORM 60: Prediction of the effects of radiation for reactor pressure vessel and in-core materials using multi-scale modelling – 60 years foreseen plant lifetime

Cited by 21 publications

References 41 publications

Current understanding of radiation-induced degradation in light water reactor structural materials

Current understanding of radiation-induced degradation in light water reactor structural materials

Magnetic Investigation of Cladded Nuclear Reactor Blocks

The Dominating Mechanisms for the Formation of Solute-Rich Clusters in Steels under Irradiation

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