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

Journal Article · · Nuclear Technology
 [1];  [2];  [2];  [2];  [1];  [3];  [4];  [4];  [4];  [4]
  1. Argonne National Lab. (ANL), Lemont, IL (United States). Mathematics and Computer Science Division
  2. Argonne National Lab. (ANL), Lemont, IL (United States). Nuclear Science and Engineering Division
  3. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  4. Texas A & M Univ., College Station, TX (United States). Nuclear Engineering Dept.
+ Show Author Affiliations

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.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA)
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
1559412
Report Number(s):
LLNL-JRNL-754259; 939716; TRN: US2000335
Journal Information:
Nuclear Technology, Vol. 205, Issue 1-2; ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)Copyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 10 works
Citation information provided by
Web of Science

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Cited By (2)

Numerical Simulation of Isothermal Flow Across Slant Five-Tube Bundle with Spectral Element Method Code Nek5000 journal July 2019
Multi-physics coupling simulation in virtual reactors journal October 2019

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