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Yu. A. Nikolaev

Bio: Yu. A. Nikolaev is an academic researcher from Kurchatov Institute. The author has contributed to research in topics: Embrittlement & Reactor pressure vessel. The author has an hindex of 10, co-authored 46 publications receiving 425 citations.

Papers
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TL;DR: In this paper, the authors analyzed the relative contributions from the following mechanisms: radiation-induced hardening, inter- and intragranular segregation of impurities at precipitate/matrix interfaces.

70 citations

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TL;DR: The contribution of irradiation-induced enrichment of grain boundaries by impurities to irradiation embrittlement of reactor pressure vessel materials is discussed in this paper, where possible mechanisms of impurities and the effect of alloying elements are considered.

40 citations

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TL;DR: In this paper, the results of Russian VVER-440 and VVER1000 surveillance programs and results of research programs on reactor pressure vessel (RPV) steel irradiation in surveillance channels of power reactors are discussed.

36 citations

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TL;DR: In this article, the effects of low-alloyed chromium-nickel-molybdenum steel on the impact transition temperature of the last generation of Russian type of reactor vessels (WWER-1000) are investigated.

30 citations

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TL;DR: In this article, electron microscopy and fractographic studies of the surveillance specimens from base and weld metals of VVER-440/213 reactor pressure vessel (RPV) in the original state and after irradiations to different fast neutron fluences from ∼5.5 MeV up to over design values have been carried out.

30 citations


Cited by
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TL;DR: In this article, the authors reviewed current phenomenological knowledge and understanding of mechanisms for radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted stress corrosion cracking of core internals of stainless steels.
Abstract: 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.

134 citations

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TL;DR: In this article, a physically-based, empirically calibrated model for estimating irradiation-induced transition temperature shifts in reactor pressure vessel steels, based on a broader database and more complete understanding of embrittlement mechanisms than was available for earlier models, is presented.

121 citations

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TL;DR: In this article, the use of microstructural features of the material, the effect of constraint and the actual region of the specimen that is undergoing deformation, and finally statistical approaches.
Abstract: The review is concerned with the use of miniature specimens to identify the mechanical/creep properties of metals and alloys. It is not intended to consider the nanoscales, which have been reviewed elsewhere, but focus on the size ranges and forms that are of use to areas such as alloy development, surveillance monitoring, effects of irradiation, properties of weld structures and remaining life. For many of these cases, there are technical advantages in the use of small specimens. Where possible, available reviews in this area are used and identified. The needs for small specimen sizes are considered, and the wide range of sizes of both conventional and more unusual specimen designs is reviewed. The potential effects of specimen size are considered: the microstructural features of the material, the effect of constraint and the actual region of the specimen that is undergoing deformation, and finally statistical approaches. The results of published studies are considered under the general groupings of yield/deformation behaviour, creep properties, toughness and fatigue, with an examination of the current state of interpretation of data from mini-specimens because interpretation is one of the key areas of interest. Finally, the current status of each area is considered, as certain designs of specimen will be better suited to answering specific technical questions. The need for standards for specific designs is also examined.

115 citations

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TL;DR: In this paper, high number densities of 2-nm-diameter Ni-, Si- and Mn-enriched nanoclusters were found in the neutron irradiated base and weld metals.

104 citations

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TL;DR: A review of the state-of-the-art of defect characterization in bulk metallic materials by positron annihilation spectroscopy is provided in this article, where the authors discuss the recent developments in the field and discuss examples of defect studies of metallic materials.

94 citations