Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD studyCitation formats

Standard

Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study. / Emad Abdelmagid Ali, Abdelmagid; Cioncolini, Andrea; Laurence, Dominique; Iacovides, Hector.

Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Brussels, Belgium, 2022.

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

Harvard

Emad Abdelmagid Ali, A, Cioncolini, A, Laurence, D & Iacovides, H 2022, Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study. in Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Brussels, Belgium, The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19), Brussels, Belgium, 6/03/22.

APA

Emad Abdelmagid Ali, A., Cioncolini, A., Laurence, D., & Iacovides, H. (2022). Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study. In Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)

Vancouver

Emad Abdelmagid Ali A, Cioncolini A, Laurence D, Iacovides H. Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study. In Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Brussels, Belgium. 2022

Author

Emad Abdelmagid Ali, Abdelmagid ; Cioncolini, Andrea ; Laurence, Dominique ; Iacovides, Hector. / Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study. Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19). Brussels, Belgium, 2022.

Bibtex

@inproceedings{c71fe5ecb2474c5a9cc1781272424b0c,
title = "Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study",
abstract = "In this work, the rotating cage (RC) setup, a well-known flow-accelerated corrosion testing system, was optimized for lead-cooled nuclear reactor applications using Computational Fluid Dynamics (CFD) simulations. The experimental setup is comprised of a fixed cylindrical vessel filled with a corrosive fluid and a rotating cage, which features testing samples manufactured from the material of interest. During operation, the relative motion between the samples and the fluid induces friction on the samples{\textquoteright} surfaces, thereby reproducing conditions found in real applications (e.g. pipes, heat exchangers and pumps). The samples normally used in the RC setup have a blunt shape with rectangular cross section. CFD analysis shows that the complex largely detached flow around this blunt shape causes a high form drag force and the power required to spin the cage becomes prohibitively large for cases with lead as a working fluid at sample speeds of 20 m/s (푅푒=2.5∗107).A more streamlined shape of the sample, with a simple to manufacture semi-circular nose and triangular trailing edge, reduces the required power by 56% and also suppresses the unsteady massive flow separations from the corners of the sample. This makes the wall shear stresses more uniform and simplifies the interpretation of corrosion measurements.",
author = "{Emad Abdelmagid Ali}, Abdelmagid and Andrea Cioncolini and Dominique Laurence and Hector Iacovides",
year = "2022",
month = mar,
day = "13",
language = "English",
booktitle = "Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)",
note = "The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19) ; Conference date: 06-03-2022 Through 11-03-2022",
url = "https://www.nureth19.com/",

}

RIS

TY - GEN

T1 - Optimized sample shape for rotating cage flow-accelerated corrosion experiments with lead: a CFD study

AU - Emad Abdelmagid Ali, Abdelmagid

AU - Cioncolini, Andrea

AU - Laurence, Dominique

AU - Iacovides, Hector

PY - 2022/3/13

Y1 - 2022/3/13

N2 - In this work, the rotating cage (RC) setup, a well-known flow-accelerated corrosion testing system, was optimized for lead-cooled nuclear reactor applications using Computational Fluid Dynamics (CFD) simulations. The experimental setup is comprised of a fixed cylindrical vessel filled with a corrosive fluid and a rotating cage, which features testing samples manufactured from the material of interest. During operation, the relative motion between the samples and the fluid induces friction on the samples’ surfaces, thereby reproducing conditions found in real applications (e.g. pipes, heat exchangers and pumps). The samples normally used in the RC setup have a blunt shape with rectangular cross section. CFD analysis shows that the complex largely detached flow around this blunt shape causes a high form drag force and the power required to spin the cage becomes prohibitively large for cases with lead as a working fluid at sample speeds of 20 m/s (푅푒=2.5∗107).A more streamlined shape of the sample, with a simple to manufacture semi-circular nose and triangular trailing edge, reduces the required power by 56% and also suppresses the unsteady massive flow separations from the corners of the sample. This makes the wall shear stresses more uniform and simplifies the interpretation of corrosion measurements.

AB - In this work, the rotating cage (RC) setup, a well-known flow-accelerated corrosion testing system, was optimized for lead-cooled nuclear reactor applications using Computational Fluid Dynamics (CFD) simulations. The experimental setup is comprised of a fixed cylindrical vessel filled with a corrosive fluid and a rotating cage, which features testing samples manufactured from the material of interest. During operation, the relative motion between the samples and the fluid induces friction on the samples’ surfaces, thereby reproducing conditions found in real applications (e.g. pipes, heat exchangers and pumps). The samples normally used in the RC setup have a blunt shape with rectangular cross section. CFD analysis shows that the complex largely detached flow around this blunt shape causes a high form drag force and the power required to spin the cage becomes prohibitively large for cases with lead as a working fluid at sample speeds of 20 m/s (푅푒=2.5∗107).A more streamlined shape of the sample, with a simple to manufacture semi-circular nose and triangular trailing edge, reduces the required power by 56% and also suppresses the unsteady massive flow separations from the corners of the sample. This makes the wall shear stresses more uniform and simplifies the interpretation of corrosion measurements.

M3 - Conference contribution

BT - Proceedings of the 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)

CY - Brussels, Belgium

T2 - The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-19)

Y2 - 6 March 2022 through 11 March 2022

ER -