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

Merzari, Elia; Yuan, Hongyong; Kraus, Adam; Obabko, Aleksandr; Fischer, Paul; Solberg, Jerome; Lee, Saya; Lai, Jonathan; Delgado, Marilyn; Hassan, Yassin A.

doi:10.1080/00295450.2018.1490124

Cited by 16 publications

(6 citation statements)

References 24 publications

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“…Moreover, this high-fidelity approach has the potential for being much more accurate than lower-fidelity FEA/CFD technologies in dealing with FIV, given the complexity of the turbulent flows under investigation. We did not limit ourselves to one-way coupling and also extended more recently to two-way coupling demonstrating that one-way coupling produced very similar results to a fully coupled solution at low flow velocity [4]. At higher speed the two-way coupling remains the only method to evaluate displacements and the overall behavior.…”

Section: Introductionmentioning

confidence: 88%

“…In this section we discuss work performed under previous years as part of the high impact problem project with the aim of providing a succinct summary of the validation status. Extensive discussion is provided in other publications [4,6,7,9].…”

Section: Overview Of Previous Validation Workmentioning

confidence: 99%

“…Work performed in the previous years have led to the development of such a tool in the multi-physics suite SHARP based on the structural code Diablo [2] and high-fidelity computational fluid dynamics code Nek5000 [3]. The FIV capability was verified on classic fluid-structure interactions (FSI) benchmark data [4].…”

Section: Introductionmentioning

confidence: 99%

“…4 illustrates the response of Node A at the 0.0% damping level for the 4 different models. Except for Model 3, the other 4 models have time histories which are almost indistinguishable, but Model 3 has displacement excursions out to 1.0E-4 meters.In order to more closely examine the response for the different analyses, PSD's were calculated for each of the analysis and presented for Models 1 -4 as Figs.…”

mentioning

confidence: 99%

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Coupled Calculations of the Nuscale FIV Tests: Pre-test Simulations and Sensitivity Analysis

Merzari

Yuan

Solberg

et al. 2018

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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 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. In particular, nuclear fuel rods and steam generators have been known to suffer from flow-induced vibration and related failures.Advanced reactors, such as integral Pressurized Water Reactors (PWRs) considered for Small Modular Reactors (SMR), often rely on innovative component designs to meet cost and safety targets. One component that is the subject of advanced designs is the steam generator, some designs of which forego the usual shell-and-tube architecture in order to fit within the primary vessel.A significant amount of data exists on flow-induced vibration in shell-and-tube heat exchangers, and heuristic methods are available to predict FIV based on a set of given assumptions. In contrast, advanced designs have far less data available. Advanced modeling and simulation based on coupled structural and fluid simulations have the potential to predict flow-induced vibration in a variety of designs, reducing the need for expensive experimental programs, especially at the conceptual design stage.

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Section: Introductionmentioning

confidence: 88%

Section: Overview Of Previous Validation Workmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

mentioning

confidence: 99%

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Coupled Calculations of the Nuscale FIV Tests: Pre-test Simulations and Sensitivity Analysis

Merzari

Yuan

Solberg

et al. 2018

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“…The flow-induced vibration (FIV) phenomenon has been a major concern for nuclear reactor safety. [89][90][91] The FIV that happens in fuel rods is especially critical. The random pressure fluctuation of the coolant often results in the vibration of fuel rods.…”

Section: Multi-physics Coupling In China Virtualmentioning

confidence: 99%

Multi-physics coupling simulation in virtual reactors

Wang

et al. 2019

SIMULATION

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Nuclear power stations involve a range of complex and interacting multi-physical processes. With the rapid development of high-performance computing technology, accurate multi-physics simulation in virtual reactors has drawn more and more attention in industry and academia. Great efforts have been made toward the simulation of multi-physics coupling processes in reactors. The interpretations of many terms that describe multi-physics simulation vary in different literatures. We organize and discuss some important terms relevant to the multi-physics coupling simulation. We compare the three most frequently used multi-physics coupling strategies: the operator splitting, Picard iteration, and Jacobian-Free Newton–Krylov methods. We summarize three main viewpoints on the degree of coupling of the three strategies (loose, tight, or full coupling). Then we review the coupling software and corresponding coupling strategies in some representative virtual reactor projects. We present the research focuses of Spider coupling platform. The Spider is developed in the China Virtual Reactor (CVR) project. The multi-physics phenomena are considered in the CVR project from three scales: fuel scale, reactor core scale, and system scale. Both loose and tight coupling strategies are supported in the Spider platform.

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