Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance

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Release : 2015
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Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance write by . This book was released on 2015. Predictive Maturity of Multi-Scale Simulation Models for Fuel Performance available in PDF, EPUB and Kindle. The project proposed to provide a Predictive Maturity Framework with its companion metrics that (1) introduce a formalized, quantitative means to communicate information between interested parties, (2) provide scientifically dependable means to claim completion of Validation and Uncertainty Quantification (VU) activities, and (3) guide the decision makers in the allocation of Nuclear Energy's resources for code development and physical experiments. The project team proposed to develop this framework based on two complimentary criteria: (1) the extent of experimental evidence available for the calibration of simulation models and (2) the sophistication of the physics incorporated in simulation models. The proposed framework is capable of quantifying the interaction between the required number of physical experiments and degree of physics sophistication. The project team has developed this framework and implemented it with a multi-scale model for simulating creep of a core reactor cladding. The multi-scale model is composed of the viscoplastic self-consistent (VPSC) code at the meso-scale, which represents the visco-plastic behavior and changing properties of a highly anisotropic material and a Finite Element (FE) code at the macro-scale to represent the elastic behavior and apply the loading. The framework developed takes advantage of the transparency provided by partitioned analysis, where independent constituent codes are coupled in an iterative manner. This transparency allows model developers to better understand and remedy the source of biases and uncertainties, whether they stem from the constituents or the coupling interface by exploiting separate-effect experiments conducted within the constituent domain and integral-effect experiments conducted within the full-system domain. The project team has implemented this procedure with the multi- scale VPSC-FE model and demonstrated its ability to improve the predictive capability of the model. Within this framework, the project team has focused on optimizing resource allocation for improving numerical models through further code development and experimentation. Related to further code development, we have developed a code prioritization index (CPI) for coupled numerical models. CPI is implemented to effectively improve the predictive capability of the coupled model by increasing the sophistication of constituent codes. In relation to designing new experiments, we investigated the information gained by the addition of each new experiment used for calibration and bias correction of a simulation model. Additionally, the variability of 'information gain' through the design domain has been investigated in order to identify the experiment settings where maximum information gain occurs and thus guide the experimenters in the selection of the experiment settings. This idea was extended to evaluate the information gain from each experiment can be improved by intelligently selecting the experiments, leading to the development of the Batch Sequential Design (BSD) technique. Additionally, we evaluated the importance of sufficiently exploring the domain of applicability in experiment-based validation of high-consequence modeling and simulation by developing a new metric to quantify coverage. This metric has also been incorporated into the design of new experiments. Finally, we have proposed a data-aware calibration approach for the calibration of numerical models. This new method considers the complexity of a numerical model (the number of parameters to be calibrated, parameter uncertainty, and form of the model) and seeks to identify the number of experiments necessary to calibrate the model based on the level of sophistication of the physics. The final component in the project team's work to improve model calibration and validation methods is the incorporation of robustness to non-probabilistic uncertainty in the input parameters. This is an improvement to model validation and uncerta ...

Multiscale Modelling Methods for Applications in Materials Science

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Release : 2013
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Book Rating : 99X/5 ( reviews)

Multiscale Modelling Methods for Applications in Materials Science - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Multiscale Modelling Methods for Applications in Materials Science write by Ivan Kondov. This book was released on 2013. Multiscale Modelling Methods for Applications in Materials Science available in PDF, EPUB and Kindle.

Improvements to the Predictive Capability of FCM Fuel Performance Modeling

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Release : 2017
Genre : Ceramic materials
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Improvements to the Predictive Capability of FCM Fuel Performance Modeling - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Improvements to the Predictive Capability of FCM Fuel Performance Modeling write by Daniel Philip Schappel. This book was released on 2017. Improvements to the Predictive Capability of FCM Fuel Performance Modeling available in PDF, EPUB and Kindle. A proposed fuel type for improved accident performance in LWRs (Light Water Reactors) involves TRISO (Tristructural-Isotropic) particles embedded in a NITE (Nano Infiltrated Eutectic) silicon carbide matrix. TRISO fuel particles contain a spherical fuel kernel of about 500 to in excess of 800 microns in diameter. The kernel and buffer layer are then coated with three isotropic layers consisting of a dense inner pyrolytic carbon (IPyC), a silicon carbide (SiC) layer, and an outer pyrolytic carbon (OPyC) layer. These layers are about 40 microns thick. The TRISO particle packing fraction in the NITE-SiC matrix is expected to be about 40 vol percent. The release of radioactivity into the coolant is dependent on the integrity of the silicon carbide layer of the TRISO particles and the NITE-SiC matrix. Currently BISON is a code being used to simulate the thermomechanical behavior of this fuel type. BISON, a code under development by Idaho National Laboratory, is built on the Multi-physics Object Oriented Simulation Environment (MOOSE). MOOSE is a massively parallel, finite element computational system that uses a Jacobian-free, Newton-Krylov (JFNK) method to solve coupled systems and non-linear partial differential equations. Due to the anisotropic geometry of the FCM pellet, the capability to model a large and random arrangement of discrete TRISO particles was developed. Additional work has been performed to develop models for the fracture of the FCM materials and transport of silver and cesium. This combination allows sufficient predictive capability to perform preliminary analysis of FCM fuel performance. TRISO FCM is predicted to perform well for linear powers less than 45 kW per meter in light water reactor environments and 15 kW per meter in high temperature gas reactors. The silicon carbide pellet is expected to limit the cesium inventory release to less than one percent in the first two days following a major accident. Future work would focus on the coupling of PyC volume change and irradiation creep effects. Coupling these effects may prevent the large stresses predicted due to rapid volume expansion. An additional objective is to design and perform experiments that show the PyC behavior at high neutron fluence.

Multiscale Modeling and Model Predictive Control of Processing Systems

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Release : 2000
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Multiscale Modeling and Model Predictive Control of Processing Systems - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Multiscale Modeling and Model Predictive Control of Processing Systems write by Orhan Ismet Karslıgil. This book was released on 2000. Multiscale Modeling and Model Predictive Control of Processing Systems available in PDF, EPUB and Kindle.

Comprehensive Nuclear Materials

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Release : 2020-07-22
Genre : Science
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Book Rating : 660/5 ( reviews)

Comprehensive Nuclear Materials - read free eBook in online reader or directly download on the web page. Select files or add your book in reader. Download and read online ebook Comprehensive Nuclear Materials write by . This book was released on 2020-07-22. Comprehensive Nuclear Materials available in PDF, EPUB and Kindle. Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field