High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors

E. Merzari, H. Yuan, A. Kraus, A. Obabko, P. Fischer, J. Solberg, S. Lee, J. Lai, M. Delgado, Y. Hassan

Research output: Contribution to journalArticle

4 Citations (Scopus)

Abstract

Flow-induced vibration (FIV) is a widespread problem in energy systems as they rely on fluid movement for energy conversion. Vibrating structures may be damaged as fatigue or wear occur. Given the importance of reliable components in the nuclear industry, FIV has long been a major concern in the safety and operation of nuclear reactors. In particular, nuclear fuel rods and steam generators have been known to suffer from FIV and related failures. In this paper we discuss the use of the computational fluid dynamics code Nek5000 coupled to the structural code Diablo to simulate the flow in helical coil heat exchangers and associated FIV. In particular, one-way coupled calculations are performed, where pressure and tractions data are loaded into the structural model. The main focus of this paper is on validation of this capability. Fluid-only Nek5000 large eddy simulations are first compared against dedicated high-resolution experiments. Then, one-way coupled calculations are performed with Nek5000 and Diablo for two data sets that provide FIV data for validation. These calculations were aimed at simulating available legacy FIV experiments in helical steam generators in the turbulent buffeting regime. In this regime one-way coupling is judged sufficient since the pressure loads do not cause substantial displacements. It is also the most common source of vibration in helical steam generators at the low flows expected in integral pressurized water reactors. We discuss validation of two-way coupled experiments and benchmarks toward the simulation of fluid elastic instability. We briefly discuss the application of these methods to grid-to-rod fretting.

Original languageEnglish (US)
Pages (from-to)33-47
Number of pages15
JournalNuclear Technology
Volume205
Issue number1-2
DOIs
StatePublished - Jan 2 2019

Fingerprint

boilers
Steam generators
reactors
vibration
Fluids
Buffeting
Nuclear industry
simulation
Experiments
Pressurized water reactors
Nuclear fuels
Large eddy simulation
Nuclear reactors
Energy conversion
Heat exchangers
Computational fluid dynamics
Wear of materials
Fatigue of materials
fluids
rods

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering
  • Condensed Matter Physics

Cite this

Merzari, E. ; Yuan, H. ; Kraus, A. ; Obabko, A. ; Fischer, P. ; Solberg, J. ; Lee, S. ; Lai, J. ; Delgado, M. ; Hassan, Y. / High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors. In: Nuclear Technology. 2019 ; Vol. 205, No. 1-2. pp. 33-47.
@article{a6be37d438cb45ec9c7ed1c8302f2e58,
title = "High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors",
abstract = "Flow-induced vibration (FIV) is a widespread problem in energy systems as they rely on fluid movement for energy conversion. Vibrating structures may be damaged as fatigue or wear occur. Given the importance of reliable components in the nuclear industry, FIV has long been a major concern in the safety and operation of nuclear reactors. In particular, nuclear fuel rods and steam generators have been known to suffer from FIV and related failures. In this paper we discuss the use of the computational fluid dynamics code Nek5000 coupled to the structural code Diablo to simulate the flow in helical coil heat exchangers and associated FIV. In particular, one-way coupled calculations are performed, where pressure and tractions data are loaded into the structural model. The main focus of this paper is on validation of this capability. Fluid-only Nek5000 large eddy simulations are first compared against dedicated high-resolution experiments. Then, one-way coupled calculations are performed with Nek5000 and Diablo for two data sets that provide FIV data for validation. These calculations were aimed at simulating available legacy FIV experiments in helical steam generators in the turbulent buffeting regime. In this regime one-way coupling is judged sufficient since the pressure loads do not cause substantial displacements. It is also the most common source of vibration in helical steam generators at the low flows expected in integral pressurized water reactors. We discuss validation of two-way coupled experiments and benchmarks toward the simulation of fluid elastic instability. We briefly discuss the application of these methods to grid-to-rod fretting.",
author = "E. Merzari and H. Yuan and A. Kraus and A. Obabko and P. Fischer and J. Solberg and S. Lee and J. Lai and M. Delgado and Y. Hassan",
year = "2019",
month = "1",
day = "2",
doi = "10.1080/00295450.2018.1490124",
language = "English (US)",
volume = "205",
pages = "33--47",
journal = "Nuclear Technology",
issn = "0029-5450",
publisher = "American Nuclear Society",
number = "1-2",

}

Merzari, E, Yuan, H, Kraus, A, Obabko, A, Fischer, P, Solberg, J, Lee, S, Lai, J, Delgado, M & Hassan, Y 2019, 'High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors', Nuclear Technology, vol. 205, no. 1-2, pp. 33-47. https://doi.org/10.1080/00295450.2018.1490124

High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors. / Merzari, E.; Yuan, H.; Kraus, A.; Obabko, A.; Fischer, P.; Solberg, J.; Lee, S.; Lai, J.; Delgado, M.; Hassan, Y.

In: Nuclear Technology, Vol. 205, No. 1-2, 02.01.2019, p. 33-47.

Research output: Contribution to journalArticle

TY - JOUR

T1 - High-Fidelity Simulation of Flow-Induced Vibrations in Helical Steam Generators for Small Modular Reactors

AU - Merzari, E.

AU - Yuan, H.

AU - Kraus, A.

AU - Obabko, A.

AU - Fischer, P.

AU - Solberg, J.

AU - Lee, S.

AU - Lai, J.

AU - Delgado, M.

AU - Hassan, Y.

PY - 2019/1/2

Y1 - 2019/1/2

N2 - Flow-induced vibration (FIV) is a widespread problem in energy systems as they rely on fluid movement for energy conversion. Vibrating structures may be damaged as fatigue or wear occur. Given the importance of reliable components in the nuclear industry, FIV has long been a major concern in the safety and operation of nuclear reactors. In particular, nuclear fuel rods and steam generators have been known to suffer from FIV and related failures. In this paper we discuss the use of the computational fluid dynamics code Nek5000 coupled to the structural code Diablo to simulate the flow in helical coil heat exchangers and associated FIV. In particular, one-way coupled calculations are performed, where pressure and tractions data are loaded into the structural model. The main focus of this paper is on validation of this capability. Fluid-only Nek5000 large eddy simulations are first compared against dedicated high-resolution experiments. Then, one-way coupled calculations are performed with Nek5000 and Diablo for two data sets that provide FIV data for validation. These calculations were aimed at simulating available legacy FIV experiments in helical steam generators in the turbulent buffeting regime. In this regime one-way coupling is judged sufficient since the pressure loads do not cause substantial displacements. It is also the most common source of vibration in helical steam generators at the low flows expected in integral pressurized water reactors. We discuss validation of two-way coupled experiments and benchmarks toward the simulation of fluid elastic instability. We briefly discuss the application of these methods to grid-to-rod fretting.

AB - Flow-induced vibration (FIV) is a widespread problem in energy systems as they rely on fluid movement for energy conversion. Vibrating structures may be damaged as fatigue or wear occur. Given the importance of reliable components in the nuclear industry, FIV has long been a major concern in the safety and operation of nuclear reactors. In particular, nuclear fuel rods and steam generators have been known to suffer from FIV and related failures. In this paper we discuss the use of the computational fluid dynamics code Nek5000 coupled to the structural code Diablo to simulate the flow in helical coil heat exchangers and associated FIV. In particular, one-way coupled calculations are performed, where pressure and tractions data are loaded into the structural model. The main focus of this paper is on validation of this capability. Fluid-only Nek5000 large eddy simulations are first compared against dedicated high-resolution experiments. Then, one-way coupled calculations are performed with Nek5000 and Diablo for two data sets that provide FIV data for validation. These calculations were aimed at simulating available legacy FIV experiments in helical steam generators in the turbulent buffeting regime. In this regime one-way coupling is judged sufficient since the pressure loads do not cause substantial displacements. It is also the most common source of vibration in helical steam generators at the low flows expected in integral pressurized water reactors. We discuss validation of two-way coupled experiments and benchmarks toward the simulation of fluid elastic instability. We briefly discuss the application of these methods to grid-to-rod fretting.

UR - http://www.scopus.com/inward/record.url?scp=85052324903&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85052324903&partnerID=8YFLogxK

U2 - 10.1080/00295450.2018.1490124

DO - 10.1080/00295450.2018.1490124

M3 - Article

AN - SCOPUS:85052324903

VL - 205

SP - 33

EP - 47

JO - Nuclear Technology

JF - Nuclear Technology

SN - 0029-5450

IS - 1-2

ER -