Coupled Calculations in Helical Steam Generator: Validation on Legacy Data

Merzari, Elia; Yuan, Hongyong; Kraus, Adam; Solberg, Jerome; Ferencz, Robert M.

doi:10.2172/1409207

Cited by 4 publications

(10 citation statements)

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“…Despite the slight deviation from uniform flow velocity in experiments, we applied a uniform flow velocity at the inlet of simulation domain. In the report [30] we discussed the application of SHARP to legacy datasets. Simulations were performed in the turbulent buffeting regime for two datasets: the B&W dataset [6] and for the Argonne dataset [7] also presented in Fig.…”

Section: Novel Bg/q Sharp Fiv Versionmentioning

confidence: 99%

“…5.4 A full system modal analysis demonstrated that these supports were too soft, as the first mode ceases to be a tube mode but instead becomes a mode of deformation of the supports themselves. A more complete analysis is included in [30].…”

Section: Structural Calculationmentioning

confidence: 99%

“…Moreover [30,31] focused on the application of SHARP to legacy datasets, in preparation for its application to the NuScale design. One-way coupled simulations were performed in the turbulent buffeting regime for two datasets: the B&W dataset [6] and the Chen et al dataset [7] ("Argonne" dataset in the following).…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Demonstration of Fully Coupled Calculations in Helical Steam Generator: Toward Predictions of Fluid Elastic Instability

E.¹,

Yuan²,

Rahaman³

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 shelland-tube architecture in order to fit within the primary vessel. In addition to being more cost-and spaceefficient, such steam generators need to be more reliable, since failure of the primary vessel represents a potential loss of coolant and a safety concern. A significant amount of data exists on flow-induced vibration in shell-and-tube heat exchangers, and heuristic methods are available to predict their occurrence 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 design stage.

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Section: Novel Bg/q Sharp Fiv Versionmentioning

confidence: 99%

Section: Structural Calculationmentioning

confidence: 99%

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Demonstration of Fully Coupled Calculations in Helical Steam Generator: Toward Predictions of Fluid Elastic Instability

E.¹,

Yuan²,

Rahaman³

et al. 2018

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“…Work performed in the previous three years led to the development of such a tool in the multi physics suite SHARP. One-way coupled calculations have been successfully performed for helical steam generators with this tool using Nek5000 and Diablo, the CFD and structural mechanics components of SHARP, respectively [1,2].…”

Section: Introductionmentioning

confidence: 99%

Nek5000 Simulations on Turbulent Coolant Flow in a Fuel Assembly Experiment - AREVA/ANL collaboration for advancing CFD tools

Makarashvili

Yuan

Merzari

et al. 2018

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“…In fact, details such as the structure of the tube supports are practically unknown. Nonetheless the report and articles [6,7] represent an important stepping stone toward the ultimate goal of simulating helical steam generators. The creation of a high-fidelity FSI solver is necessary because the semi-empirical approaches that have been applied to traditional heat exchangers are not applicable to helical coil SGs.…”

Section: Introductionmentioning

confidence: 99%

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

Merzari

Yuan

Solberg

et al. 2018

View full text Add to dashboard Cite

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.

show abstract

Coupled Calculations in Helical Steam Generator: Validation on Legacy Data

Cited by 4 publications

References 0 publications

Demonstration of Fully Coupled Calculations in Helical Steam Generator: Toward Predictions of Fluid Elastic Instability

Demonstration of Fully Coupled Calculations in Helical Steam Generator: Toward Predictions of Fluid Elastic Instability

Nek5000 Simulations on Turbulent Coolant Flow in a Fuel Assembly Experiment - AREVA/ANL collaboration for advancing CFD tools

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

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