Analysis of Fluid-structure Interaction in a Sodium Fast Reactor Core

Analysis of Fluid-structure Interaction in a Sodium Fast Reactor Core PDF Author: Qing Zhou
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ISBN:
Category :
Languages : en
Pages : 0

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Book Description
In the scheme of French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project, fluid-structure interaction phenomena involved in the dynamic behaviour of core flowering, which could happen during seismic events, are of high interest. Also core flowering behaviour is considered as the main initiating event for the four SCRAMs that happened in Phénix reactor during 1989 and 1990. In objective to improve the knowledge of fluid-structure interaction phenomena of dynamic issues in a SFR core, especially focused on damping, this Ph.D. thesis have been conducted in experimental, numerical and analytical approaches based on free-vibration experiments on mono-assembly test facility PISE-1A and multi-assembly test facility PISE-2C. Two series of free-vibration experiments have been performed on PISE-1A with different water heights and different mass fractions of water-glycerol mixtures to examine the dynamic behaviours with respect to different added mass, different densities and viscosities. Corresponding numerical interpretations have been conducted with 3D Navier-Stokes model in CAST3M code. Sources of uncertainties are discussed to explain the discrepancies between the numerical computation and experimental results. Edge effects are not found to have an important impact on the dynamic behaviours of the system. On PISE-2C, free-vibration experiments with different modes of excitations have been conducted, including total flowering, partial flowering with internal crown excited and partial flowering with external crown excited. A reticulate model with homogenised linear hypothesis has been developed to interpret PISE-2C experiments. Good symmetries are found in PISE-2C suggesting that the deterministic tool is valid for the analysis.

Analysis of Fluid-structure Interaction in a Sodium Fast Reactor Core

Analysis of Fluid-structure Interaction in a Sodium Fast Reactor Core PDF Author: Qing Zhou
Publisher:
ISBN:
Category :
Languages : en
Pages : 0

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Book Description
In the scheme of French ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) project, fluid-structure interaction phenomena involved in the dynamic behaviour of core flowering, which could happen during seismic events, are of high interest. Also core flowering behaviour is considered as the main initiating event for the four SCRAMs that happened in Phénix reactor during 1989 and 1990. In objective to improve the knowledge of fluid-structure interaction phenomena of dynamic issues in a SFR core, especially focused on damping, this Ph.D. thesis have been conducted in experimental, numerical and analytical approaches based on free-vibration experiments on mono-assembly test facility PISE-1A and multi-assembly test facility PISE-2C. Two series of free-vibration experiments have been performed on PISE-1A with different water heights and different mass fractions of water-glycerol mixtures to examine the dynamic behaviours with respect to different added mass, different densities and viscosities. Corresponding numerical interpretations have been conducted with 3D Navier-Stokes model in CAST3M code. Sources of uncertainties are discussed to explain the discrepancies between the numerical computation and experimental results. Edge effects are not found to have an important impact on the dynamic behaviours of the system. On PISE-2C, free-vibration experiments with different modes of excitations have been conducted, including total flowering, partial flowering with internal crown excited and partial flowering with external crown excited. A reticulate model with homogenised linear hypothesis has been developed to interpret PISE-2C experiments. Good symmetries are found in PISE-2C suggesting that the deterministic tool is valid for the analysis.

Analysis of Nonlinear Fluid Structure Interaction Transient in Fast Reactors

Analysis of Nonlinear Fluid Structure Interaction Transient in Fast Reactors PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Book Description
A generalized Eulerian method is described for analyzing the fluid transients and the structural response in nuclear reactors under the postulated accident conditions. The phenomena considered are the wave propagation, slug impact, sodium spillage, bubble migration, and the fluid-structure interaction. The basic equations and numerical formulation are presented in detail. Sample calculations are given to illustrate the analysis. It is shown from the results that the implicit, iterative method used is unconditionally stable and is especially suitable for problems involving large material distortions.

Numerical Simulation of Fluid-Structure Interaction During the Expansion Phase in Sodium Cooled Fast Reactors

Numerical Simulation of Fluid-Structure Interaction During the Expansion Phase in Sodium Cooled Fast Reactors PDF Author: Maximilian Hartig
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ISBN:
Category :
Languages : en
Pages :

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Fluid-Structure Interaction for Coolant Flow in Research-type Nuclear Reactors

Fluid-Structure Interaction for Coolant Flow in Research-type Nuclear Reactors PDF Author:
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ISBN:
Category :
Languages : en
Pages :

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Book Description
The High Flux Isotope Reactor (HFIR), located at the Oak Ridge National Laboratory (ORNL), is scheduled to undergo a conversion of the fuel used and this proposed change requires an extensive analysis of the flow through the reactor core. The core consists of 540 very thin and long fuel plates through which the coolant (water) flows at a very high rate. Therefore, the design and the flow conditions make the plates prone to dynamic and static deflections, which may result in flow blockage and structural failure which in turn may cause core damage. To investigate the coolant flow between fuel plates and associated structural deflections, the Fluid-Structure Interaction (FSI) module in COMSOL will be used. Flow induced flutter and static deflections will be examined. To verify the FSI module, a test case of a cylinder in crossflow, with vortex induced vibrations was performed and validated.

Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles

Coolant Mixing in Sodium Cooled Fast Reactor Fuel Bundles PDF Author: Neil E. Todreas
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ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 76

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Fluid-structure Interactions in Pressure-suppression Pools

Fluid-structure Interactions in Pressure-suppression Pools PDF Author: P. W. Huber
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ISBN:
Category : Boiling water reactors
Languages : en
Pages : 92

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Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics

Analysis of Advanced Sodium-cooled Fast Reactor Core Designs with Improved Safety Characteristics PDF Author: Kaichao Sun
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ISBN:
Category :
Languages : en
Pages : 180

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Eulerian Algorithm for Analyzing Fluid-structure Interaction in the Fast Reactor Containment

Eulerian Algorithm for Analyzing Fluid-structure Interaction in the Fast Reactor Containment PDF Author:
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Category :
Languages : en
Pages :

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The Eulerian algorithm described is capable of analyzing two-dimensionally the fluid-structure interaction in a typical LMFBR containment consisting of various structure components. The algorithm has several special features. First, it employs the Eulerian coordinates in the formulation and enables the technique to be applicable to excursions involving large material distortions. Second, it provides rigorous hydrodynamic analyses at the fluid-structure interface and at the geometrical discontinuities, which is very important in the study of wave-transmission and -diffraction problems. Third, the algorithm incorporates a well-developed finite-element structural program that can account for both material and geometrical nonlinearities. The application of this Eulerian algorithm is not limited to fast reactor containment. It can also be applied to the major piping components, such as valve and IHX, where internal baffle plates may play an important role in the wave propagation. Moreover, the treatment of the time-dependent irregular cell can be integrated with the IMF2 Method and structural dynamics program for investigating the coupled fluid-structure problems involving two-phase flows.

Oscillation Measurements in the Sodium Reactor Experiment

Oscillation Measurements in the Sodium Reactor Experiment PDF Author: C. W. Griffin
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ISBN:
Category : Nuclear reactors
Languages : en
Pages : 30

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Analyses of Fluid-structure Interaction and Structural Response of Reactor Vessel to a Postulated Accident

Analyses of Fluid-structure Interaction and Structural Response of Reactor Vessel to a Postulated Accident PDF Author: C. Y. Wang
Publisher:
ISBN:
Category :
Languages : en
Pages : 7

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