Revision of the irradiation embrittlement correlation used for the EDF RPV fleet

Todeschini, Patrick; Lefebvre, Yannick; Churier-Bossennec, Henriette; Rupa, Nathalie; Chas, Guillaume; Benhamou, Claude Laurent

doi:10.1051/rgn/20111029

Cited by 15 publications

(6 citation statements)

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“…In this curve, the Cu content for CRPs, and Ni content and temperature for MD are included. Modification of the prediction equations or trend curves is being discussed in other European countries based on an empirical formulation using fluence and chemical factors [134][135][136][137].…”

Section: Transition Temperature Shiftmentioning

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: Transition Temperature Shiftmentioning

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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“…Table 2: Irradiation conditions of the materials: Material #1 has been irradiated as part of the EDF surveillance program [6], Material #2 has been irradiated in MTRs [42,45] In the range considered in Tab. 2, fast neutron flux has been shown to have a negligible effect on irradiation-induced hardening and embrittlement for low copper materials [10]. Thus, the difference between Materials #1 and #2 specimens reported hereafter are mainly fast neutron fluence, and to a lesser extent chemical composition.…”

Section: Methodsmentioning

confidence: 87%

“…The functions α(Φ) and β(Φ) require calibration. A power-law dependence to the fast neutron fluence with an exponent 0.59 is chosen, consistently with the ETC [10]. Only the two prefactors of the functions α(Φ) and β(Φ) remain to be calibrated, which has been done in [42] for a fluence of 12.10 19 n.cm −2 .…”

Section: Calibration: Hardening Behaviormentioning

confidence: 99%

“…Various analytical models, loosely referred to as Embrittlement Trend Curves (ETC) in the following, have been proposed to predict the temperature shift ∆T . Statistical analysis of extended experimental database leads to NUREG-6551 [9] and FIM [10] semi-empirical correlations, based on US and France data, respectively. Physically-based correlations have also been proposed, such as the JEAC4201 model relying on the quantification of irradiation defects [11] or the EONY model [12].…”

Section: Introductionmentioning

confidence: 99%

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Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

Hure

Parrot

Meunier

2022

Journal of Nuclear Materials

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“…It is well accepted that high flux has to be used carefully to predict the in-service behavior of RPV steels with high Cu content (e.g., [156,157,158,159]). Conversely, several studies showed that embrittlement of steels with low Cu is weakly sensitive to flux (e.g., [153,154,160,161,162]…”

Section: Flux Effectmentioning

confidence: 99%

60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

Duysen

Bellefon

2017

Journal of Nuclear Materials

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The first light water nuclear reactor dedicated to electricity production was commissioned in Shippingport, Pennsylvania in the United States in 1957. Sixty years after the event, it is clear that this type of reactor will be a major source of electricity and one of the key solutions to limit climate change in the 21 st century. This article pays homage to the teams that contributed to this achievement by their involvement in research and development and their determination to push back the frontiers of knowledge. Via a few examples of scientific or technological milestones, it describes the evolution of ideas, models, and techniques during the last 60 years, and gives the current state-of-the-art in areas related to the safety of the reactor pressure vessel. Among other topics, it focuses on vessel manufacturing, steel fracture mechanics analysis, and understanding of irradiation-induced damage.

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Revision of the irradiation embrittlement correlation used for the EDF RPV fleet

Cited by 15 publications

References 0 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

Numerical prediction of the effect of irradiation on the Charpy Upper Shelf Energy of Reactor Pressure Vessel steels

60th Anniversary of electricity production from light water reactors: Historical review of the contribution of materials science to the safety of the pressure vessel

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