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| Naji, M. |
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| Motta, Antonella |
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| Aletan, Dirar |
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| Mohamed, Tarek |
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| Ertürk, Emre |
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| Taccardi, Nicola |
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| Kononenko, Denys |
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| Petrov, R. H. | Madrid |
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| Alshaaer, Mazen | Brussels |
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| Bih, L. |
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| Casati, R. |
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| Muller, Hermance |
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| Kočí, Jan | Prague |
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| Šuljagić, Marija |
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| Kalteremidou, Kalliopi-Artemi | Brussels |
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| Azam, Siraj |
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| Ospanova, Alyiya |
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| Blanpain, Bart |
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| Ali, M. A. |
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| Popa, V. |
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| Rančić, M. |
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| Ollier, Nadège |
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| Azevedo, Nuno Monteiro |
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| Landes, Michael |
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| Rignanese, Gian-Marco |
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Daly, Michael
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (12/12 displayed)
- 2024Mechanical and crystallization properties of hot runner injection molded virgin and recycled polypropylenecitations
- 2021Acute and longer-term psychological distress associated with testing positive for COVID-19: longitudinal evidence from a population-based study of US adultscitations
- 2017A multi-scale correlative investigation of ductile fracturecitations
- 2017Degradation of metallic materials studied by correlative tomographycitations
- 2016Synthesis and characterization of high density polyethylene/peat ash compositescitations
- 2016Chemical surface modification of calcium carbonate particles with stearic acid using different treating methodscitations
- 2016Characteristics of the treated calcium carbonate particles with stearic acid using different treating methods. ; Chemical surface modification of calcium carbonate particles with stearic acid using different treating methods
- 2015Large volume serial section tomography by Xe Plasma FIB dual beam microscopycitations
- 2015Large volume serial section tomography by Xe Plasma FIB dual beam microscopycitations
- 2013Advanced assessment of the ductile fracture mechanism in A508 class 3 reactor pressure vessel steel using laboratory X-ray tomographycitations
- 2013Advanced assessment of ductile tearing in nuclear reactor pressure vessel steel using x-ray tomography
- 2012Advanced assessment of the integrity of ductile components
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document
Advanced assessment of the integrity of ductile components
Abstract
Nuclear Reactor Pressure Vessels (RPV) are manufactured from medium strength low alloy ferritic steel, specifically selected for its high toughness and good weldability. The ability of the pressure vessel to resist crack growth is crucial given that it is one of the fundamental containment safety systems of the reactor. For most of their lifetime, the pressure vessel operates at sufficiently elevated temperatures to ensure the material is ductile. However, the development of ductile damage, in the form of voids, and the ability to predict the ductile crack growth in RPV materials requires further work. The Gurson-Tvergaard-Needleman (GTN) model of void nucleation, growth and coalescence provides one tool for predicting ductile damage development. The model is normally calibrated against fracture toughness test data. However, recent work [1] has demonstrated the benefit of refining calibrations against measured void volume fractions generated from notched and pre-cracked specimen tests. This paper described the measurement of void distributions below the fracture surface of a range of notched and precracked specimens. The void distribution below the fracture surface is shown to be dependent upon the local stress triaxiality and plastic strain distribution. As a result, precracked specimens show a greater concentration of voids close to the fracture surface, whilst notched tensile specimens show a lower volume fraction of voids close to the crack surface. In both specimen types, voids are observed to extend between 2.5 and 3.5 mm below the fracture surface.