Feasibility of Dynamic Testing of As-built Nuclear Power Plant Structures PDF Download
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Author: Muthukrishnan Gopalsamy Srinivasan
Publisher:
ISBN:
Category : Engineering design
Languages : en
Pages : 64
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Book Description
Author: Muthukrishnan Gopalsamy Srinivasan
Publisher:
ISBN:
Category : Engineering design
Languages : en
Pages : 64
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Book Description
Author: H. Joseph Weaver
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 44
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Author: M. G. Srinivasan
Publisher:
ISBN:
Category :
Languages : en
Pages : 0
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Author:
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ISBN:
Category :
Languages : en
Pages :
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Book Description
Lawrence Livermore Laboratory (LLL) evaluated the applications of system identification techniques to the dynamic testing of nuclear power plant structures and subsystems. These experimental techniques involve exciting a structure and measuring, digitizing, and processing the time-history motions that result. The data can be compared to parameters calculated using finite element or other models of the test systems to validate the model and to verify the seismic analysis. This report summarizes work in three main areas: (1) analytical qualification of a set of computer programs developed at LLL to extract model parameters from the time histories; (2) examination of the feasibility of safely exciting nuclear power plant structures and accurately recording the resulting time-history motions; (3) study of how the model parameters that are extracted from the data be used best to evaluate structural integrity and analyze nuclear power plants.
Author: U.S. Nuclear Regulatory Commission
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 64
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Book Description
Author: D. A. Wesley
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 88
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Author: Paul Ibáñez
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 152
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Author: G. Bagchi
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 72
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Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
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The analytical evaluation of two particular system identification codes used at Lawrence Livermore Laboratory is presented. Both codes are eigenparameter identification codes; however, one uses a time domain approach while the other a frequency domain approach. The evaluation was accomplished by analytically generating several time history signals in which the true modal parameters were known. These time histories ranged from widely spaced modes with spacing factors of 100 percent to closely spaced modes with spacing factors of 6 percent. These signals were then polluted with various levels of simulated measurement noise and the ability of our computer codes to extract the parameters from this noisy data was evaluated.
Author: Eric C. Althoff
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 253
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Book Description
Probability risk assessment (PRA) of nuclear power plants (NPP) has been used since the mid-1970s to evaluate the associated risks or perform a risk-informed design of NPPs. Since its inception, PRA has considered both internal and external events to evaluate the risks to a NPP site. However, external event PRA has historically been recognized as having considerable safety margin until recent events have emphasized the need for a reevaluation. This research is part of a larger project with the goal of incorporating internal and external event PRA in a common platform using state-of-the-art methods. Specifically, the focus of the research in this thesis was to develop and evaluate structural models with different levels of complexity for several structures that are vital for seismic probabilistic risk assessment (SPRA) of NPPs. For SPRA, critical structures, systems, and components (SSCs) are investigated to evaluate their risk during seismic events. To evaluate the risk of critical SSCs, structural models are needed to predict their dynamic behavior. However, due to the large number of analyses required during SPRA, simple yet sufficient models are desired to increase the computational efficiency and reduce the run-time of models. As such, the focus of this research was to develop simple yet sufficiently accurate structural models for SSCs and to evaluate the uncertainty related to those models. Three critical NPP structures are investigated in this research to illustrate the capabilities and limitations of models with varying levels of complexity. The structures included a condensate storage tank (CST), auxiliary building, and containment structure. Realistic geometric and material properties for each structure are introduced, and both detailed three-dimensional (3D) and simplified two-dimensional (2D) models are created. Detailed 3D finite element (FE) models incorporated complex mechanical behavior such as fluid-structure interaction and slab flexibility. Simplified 2D models developed included lumped-mass stick models and lumped-mass-spring systems. Modal and time history analyses are used to evaluate and compare the dynamic behavior and response of both detailed and simplified models to seismic events, and the capabilities and limitations of simplified models are investigated. For CSTs, several available simplified lumped-mass-spring systems are developed and compared to a 3D FE model that incorporated fluid-structure interaction. Critical failure modes for CSTs are investigated using simplified and detailed models to illustrate key differences in the models. For auxiliary buildings, several different 3D building models are developed to illustrate the effects of structural irregularity and slab flexibility on simplified models. The importance of detailed 3D models is illustrated through spatial response of the 3D models compared to the singular response of simplified stick models. Finally, simplified and detailed models for a containment structure are developed. Lumped-mass stick and 3D FE models are developed to evaluate the dynamic behavior and response of each. A polar crane system is later added to one of the 3D FE models to investigate its potential failure modes. For each structure developed, the limitations and capabilities of simplified models are evaluated, and certain scenarios where simplified models are insufficient for SPRA are illustrated.Less
