One-Way Coupled Flow-Induced Vibration Analysis for a Twisted-Tube Heat Exchanger
- Argonne National Laboratory (ANL), Argonne, IL (United States)
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
The NEAMS program aims to develop an integrated multi-physics simulation capability “pellet-to-plant” for the design and analysis of future generations of nuclear power plants. In particular, the Reactor Product Line code suite's multi-resolution hierarchy is being designed to ultimately span the full range of length and time scales present in relevant reactor design and safety analyses, as well as scale from desktop to petaflop computing platforms. Flow-induced vibration (FIV) is a widespread problem in energy systems because they rely on fluid movement for energy conversion. Vibrating structures may be damaged as fatigue or wear occurs. Given the importance of reliable components in the nuclear industry, flow-induced vibration has long been a major concern in safety and operation of nuclear reactors. Nuclear fuel rods and steam generators have been known to suffer from flow-induced vibration and related failures.
- Research Organization:
- Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Argonne National Laboratory (ANL), Argonne, IL (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC)
- DOE Contract Number:
- AC52-07NA27344; AC02-06CH11357
- OSTI ID:
- 1572624
- Report Number(s):
- LLNL-TR-795710; 992481
- Country of Publication:
- United States
- Language:
- English
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