Technologies in Reactor Safety, Fluid-structure Interaction, Sloshing and Natural Hazards Engineering


Book Description

Thirty-six contributions from the July 1998 Conference present an analysis of dynamic systems and fluid-structure interaction in reactor technology and fluid-structure interaction. Most of the papers reflect how advances in these fields of research, as a result of the development of high-performance computers and methods of experiment, lead to detailed results that could not have otherwise been obtained. Topics are divided into two sections--technologies in reactor safety and natural hazards engineering, and fluid-structure interaction and sloshing. Concludes with two student papers. Contains an author index but no subject index. Annotation copyrighted by Book News, Inc., Portland, OR




Structures Under Extreme Loading Conditions, Fluid-structure Interaction, and Structural Mechanics Problems in Reactor Safety 1999


Book Description

Papers from an August 1999 conference examine areas including supersonic penetration of shaped charge jets into concrete, scaling blast-induced wall loadings in a rectangular room, a damage model for composites under dynamic loading, nonlinear analysis of EFB phenomena of cylindrical storage tanks d




Index of Conference Proceedings


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AIAA Journal


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


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.







Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment


Book Description

Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies. It includes an evaluation of safety systems for reactors using CFD and their design, the modeling of Severe Accident Phenomena Using CFD, Model Development for Two-phase Flows, and Applications for Sodium and Molten Salt Reactor Designs. Editors Joshi and Nayak have an invaluable wealth of experience that enables them to comment on the development of CFD models, the technologies currently in practice, and the future of CFD in nuclear reactors. Readers will find a thematic discussion on each aspect of CFD applications for the design and safety assessment of Gen II to Gen IV reactor concepts that will help them develop cost reduction strategies for nuclear power plants. Presents a thematic and comprehensive discussion on each aspect of CFD applications for the design and safety assessment of nuclear reactors Provides an historical review of the development of CFD models, discusses state-of-the-art concepts, and takes an applied and analytic look toward the future Includes CFD tools and simulations to advise and guide the reader through enhancing cost effectiveness, safety and performance optimization