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Fluence rate effects on irradiation embrittlement of model alloys

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TLDR
In this paper, a parametric study of the response to neutron irradiation of 32 different model alloys with systematic variation of elements (Ni from 0.004 to ∼2.5 kg, P from 0.,001 to 0.039 kg, Cu from 0,005 to ∼1.1 kg) was performed in the LYRA rig at the High Flux Reactor (HFR) of the Joint Research Centre, Petten, The Netherlands.
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This article is published in International Journal of Pressure Vessels and Piping.The article was published on 2005-05-01. It has received 7 citations till now. The article focuses on the topics: Embrittlement & Reactor pressure vessel.

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On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models

TL;DR: In this article, the authors present an overview of the history of Reactor Pressure Vessel (RPV) embrittlement research, focusing on predicting ductile-to-brittle transition temperature shifts (ΔT), along with an assessment of the current status of these efforts, especially for extended life operation.
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Effect of Irradiation Temperature in PWR RPV Materials and its Inclusion in Semi-Mechanistic Model

TL;DR: In this paper, the authors presented a semi-mechanistic model for radiation embrittlement, where the irradiation temperature is included into a general semi-Meanistic model.
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Effects of neutron flux on irradiation-induced hardening and defects in RPV steels studied by positron annihilation spectroscopy

TL;DR: In this paper, the authors studied the effects of neutron-flux effects on irradiation-induced hardening and microstructures in a reactor pressure vessel steel and showed that defects in which positrons are trapped are the origin of irradiation hardening.
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Analysis of WWER-440 and PWR RPV welds surveillance data to compare irradiation damage evolution

TL;DR: In this paper, a semi-mechanistic model for radiation embrittlement developed by JRC-IE has been used to compare irradiation damage evolution for different reactor pressure vessel welds.
References
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Irradiation embrittlement of model alloys and commercial steels: analysis of similitude behaviors

TL;DR: In this article, a parametric study of the response to neutron irradiation of 32 different model alloys with parametric variation of elements (Ni from 0.004 to ∼2.2
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LYRA and other projects on RPV steel embrittlement: Study and mitigation of the AMES Network

TL;DR: In this paper, the authors present the main and spin-off projects of the European Network Ageing Materials Evaluation and Studies (AME), including a brief description on the modelling activities related to RPV materials embrittlement.
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Advanced method for WWER RPV embrittlement assessment

TL;DR: In this paper, a semi-mechanistic model is proposed to predict embrittlement and re-embrittlement after annealing of high P materials typical of certain VVER-440 RPVs.
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Evaluation of irradiation damage effect by applying electric properties based techniques

TL;DR: In this paper, the authors compared the results of the impact tests, STEAM and REAM measurements with the change in the mechanical properties due to neutron irradiation in order to assess non-destructively the embrittlement state of materials.
Journal ArticleDOI

Development of the AMES network throughout the 4th and 5th EURATOM framework programmes

TL;DR: The AMES (Ageing Materials European Strategy ) network started its activity in 1993 with the aim of studying ageing mechanisms and remedial procedures for structural materials used for nuclear reactor components.
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