Numerical Simulation of Fluid-Structure Interaction During the Expansion Phase in Sodium Cooled Fast Reactors PDF Download
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Author: Maximilian Hartig
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Languages : en
Pages :
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Author: Maximilian Hartig
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Languages : en
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Author: Qing Zhou
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Languages : en
Pages : 0
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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.
Author: Aakanksha Saxena
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Languages : en
Pages : 0
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The thesis focuses on the numerical simulation of sodium flow in wire wrapped sub-assembly of Sodium-cooled Fast Reactor (SFR).First calculations were carried out by a time averaging approach called RANS (Reynolds- Averaged Navier-Stokes equations) using industrial code STAR-CCM+. This study gives a clear understanding of heat transfer between the fuel pin and sodium. The main variables of the macroscopic flow are in agreement with correlations used hitherto. However, to obtain a detailed description of temperature fluctuations around the spacer wire, more accurate approaches like LES (Large Eddy Simulation) and DNS (Direct Numerical Simulation) are clearly needed. For LES approach, the code TRIO_U was used and for the DNS approach, a research code was used. These approaches require a considerable long calculation time which leads to the need of representative but simplified geometry.The DNS approach enables us to study the thermal hydraulics of sodium that has very low Prandtl number inducing a very different behavior of thermal field in comparison to the hydraulic field. The LES approach is used to study the local region of sub-assembly. This study shows that spacer wire generates the local hot spots (~20°C) on the wake side of spacer wire with respect to the sodium flow at the region of contact with the fuel pin. Temperature fluctuations around the spacer wire are low (~1-2°C). Under nominal operation, the spectral analysis shows the absence of any dominant peak for temperature oscillations at low frequency (2-10Hz). The obtained spectra of temperature oscillations can be used as an input for further mechanical studies to determine its impact on the solid structures.
Author: Tromm, Walter
Publisher: KIT Scientific Publishing
ISBN: 3731510499
Category : Technology & Engineering
Languages : en
Pages : 90
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The annual report of the Institute for Nuclear and Energy Technologies of KIT summarizes its research activities and provides some highlights of each working group, like thermal-hydraulic analyses for fusion reactors, accident analyses for light water reactors, and research on innovative energy technologies: liquid metal technologies for energy conversion, hydrogen technologies and geothermal power plants. The institute has been engaged in education and training in energy technologies.
Author: Neil E. Todreas
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Category : Nuclear fuel elements
Languages : en
Pages : 76
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Languages : en
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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.
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Category : Nuclear energy
Languages : en
Pages : 682
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Languages : en
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Three-dimensional, coupled, fluid-structure calculations were performed for the dynamics of the core support barrel in an HDR reactor vessel during blowdown. For these calculations the three-dimensional, two-fluid code K-FIX was coupled to the three-dimensional elastic shell code FLX. The coupling procedure is described, and conditions derived from truncation error and Fourier analysis are given for numerical stability of the separate and coupled finite difference solution algorithms. The results demonstrate the importance of the coupled interactions on the structural response. A nodalization study indicates the degree of circumferential and axial resolution required for accurate results. Fine axial resolution is needed near the top built-in boundary of the core barrel to determine stresses accurately, but it is less necessary for displacements.
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Category : Power resources
Languages : en
Pages : 748
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Author: Xingyuan Chen
Publisher:
ISBN:
Category :
Languages : en
Pages : 171
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