Verification Validation and Uncertainty Quantification of Multi Physics Modeling of Nuclear Reactors

Verification  Validation and Uncertainty Quantification of Multi Physics Modeling of Nuclear Reactors
Author: Maria Avramova,Kostadin Ivanov
Publsiher: Woodhead Publishing Series in
Total Pages: 300
Release: 2018-09-15
ISBN 10: 9780128149546
ISBN 13: 012814954X
Language: EN, FR, DE, ES & NL

Verification Validation and Uncertainty Quantification of Multi Physics Modeling of Nuclear Reactors Book Review:

Verification, Validation and Uncertainty Quantification in Multi-Physics Modeling of Nuclear Reactors is a key reference for those tasked with ensuring the credibility and reliability of engineering models and simulations for the nuclear industry and nuclear energy research. Sections discuss simulation challenges and revise key definitions, concepts and terminology. Chapters cover solution verification, the frontier discipline of multi-physics coupling verification, model validation and its applications to single and multi-scale models, and uncertainty quantification. This essential guide will greatly assist engineers, scientists, regulators and students in applying rigorous verification, validation and uncertainty quantification methodologies to the M&S tools used in the industry. The book contains a strong focus on the verification and validation procedures required for the emerging multi-physics M&S tools that have great potential for use in the licensing of new reactors, as well as for power uprating and life extensions of operating reactors. Uniquely--and crucially for nuclear engineers--demonstrates the application of verification, validation and uncertainty methodologies to the modeling and simulation (M&S) of nuclear reactors Equips the reader to develop a rigorously defensible validation process irrespective of the particular M&S tool used Brings the audience up-to-speed on validation methods for traditional M&S tools Extends the discussion to the emerging area of validation of multi-physics and multi-scale nuclear reactor simulations

Improved Best Estimate Plus Uncertainty Methodology Including Advanced Validation Concepts to License Evolving Nuclear Reactors

Improved Best Estimate Plus Uncertainty Methodology Including Advanced Validation Concepts to License Evolving Nuclear Reactors
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2010
ISBN 10: 1928374650XXX
ISBN 13: OCLC:873865836
Language: EN, FR, DE, ES & NL

Improved Best Estimate Plus Uncertainty Methodology Including Advanced Validation Concepts to License Evolving Nuclear Reactors Book Review:

Many evolving nuclear energy programs plan to use advanced predictive multi-scale multi-physics simulation and modeling capabilities to reduce cost and time from design through licensing. Historically, the role of experiments was primary tool for design and understanding of nuclear system behavior while modeling and simulation played the subordinate role of supporting experiments. In the new era of multi-scale multi-physics computational based technology development, the experiments will still be needed but they will be performed at different scales to calibrate and validate models leading predictive simulations. Cost saving goals of programs will require us to minimize the required number of validation experiments. Utilization of more multi-scale multi-physics models introduces complexities in the validation of predictive tools. Traditional methodologies will have to be modified to address these arising issues. This paper lays out the basic aspects of a methodology that can be potentially used to address these new challenges in design and licensing of evolving nuclear technology programs. The main components of the proposed methodology are verification, validation, calibration, and uncertainty quantification. An enhanced calibration concept is introduced and is accomplished through data assimilation. The goal is to enable best-estimate prediction of system behaviors in both normal and safety related environments. To achieve this goal requires the additional steps of estimating the domain of validation and quantification of uncertainties that allow for extension of results to areas of the validation domain that are not directly tested with experiments, which might include extension of the modeling and simulation (M & S) capabilities for application to full-scale systems. The new methodology suggests a formalism to quantify an adequate level of validation (predictive maturity) with respect to required selective data so that required testing can be minimized for cost saving purposes by showing further testing wold not enhance the quality of the validation of predictive tools. The proposed methodology is at a conceptual level. When matured and if considered favorably by the stakeholders, it could serve as a new framework for the next generation of the best estimate plus uncertainty licensing methodology that USNRC developed previously. In order to come to that level of maturity it is necessary to communicate the methodology to scientific, design and regulatory stakeholders for discussion and debates. This paper is the first step to establish this communication.

Uncertainty Quantification in Multiscale Materials Modeling

Uncertainty Quantification in Multiscale Materials Modeling
Author: Yan Wang,David L. McDowell
Publsiher: Woodhead Publishing
Total Pages: 604
Release: 2020-03-10
ISBN 10: 008102942X
ISBN 13: 9780081029428
Language: EN, FR, DE, ES & NL

Uncertainty Quantification in Multiscale Materials Modeling Book Review:

Uncertainty Quantification in Multiscale Materials Modeling provides a complete overview of uncertainty quantification (UQ) in computational materials science. It provides practical tools and methods along with examples of their application to problems in materials modeling. UQ methods are applied to various multiscale models ranging from the nanoscale to macroscale. This book presents a thorough synthesis of the state-of-the-art in UQ methods for materials modeling, including Bayesian inference, surrogate modeling, random fields, interval analysis, and sensitivity analysis, providing insight into the unique characteristics of models framed at each scale, as well as common issues in modeling across scales. Synthesizes available UQ methods for materials modeling Provides practical tools and examples for problem solving in modeling material behavior across various length scales Demonstrates UQ in density functional theory, molecular dynamics, kinetic Monte Carlo, phase field, finite element method, multiscale modeling, and to support decision making in materials design Covers quantum, atomistic, mesoscale, and engineering structure-level modeling and simulation

Model Validation and Uncertainty Quantification Volume 3

Model Validation and Uncertainty Quantification  Volume 3
Author: H. Sezer Atamturktur,Babak Moaveni,Costas Papadimitriou,Tyler Schoenherr
Publsiher: Springer Science & Business Media
Total Pages: 427
Release: 2014-04-11
ISBN 10: 3319045520
ISBN 13: 9783319045528
Language: EN, FR, DE, ES & NL

Model Validation and Uncertainty Quantification Volume 3 Book Review:

This third volume of eight from the IMAC - XXXII Conference, brings together contributions to this important area of research and engineering. The collection presents early findings and case studies on fundamental and applied aspects of Structural Dynamics, including papers on: Linear Systems Substructure Modelling Adaptive Structures Experimental Techniques Analytical Methods Damage Detection Damping of Materials & Members Modal Parameter Identification Modal Testing Methods System Identification Active Control Modal Parameter Estimation Processing Modal Data

Expansion of the Severe Accident Code MELCOR by Coupling External Models

Expansion of the Severe Accident Code MELCOR by Coupling External Models
Author: Dietrich, Philipp
Publsiher: KIT Scientific Publishing
Total Pages: 162
Release: 2017-02-20
ISBN 10: 3731506033
ISBN 13: 9783731506034
Language: EN, FR, DE, ES & NL

Expansion of the Severe Accident Code MELCOR by Coupling External Models Book Review:

Assessing the Reliability of Complex Models

Assessing the Reliability of Complex Models
Author: National Research Council,Division on Engineering and Physical Sciences,Board on Mathematical Sciences and Their Applications,Committee on Mathematical Foundations of Verification, Validation, and Uncertainty Quantification
Publsiher: National Academies Press
Total Pages: 144
Release: 2012-07-26
ISBN 10: 0309256348
ISBN 13: 9780309256346
Language: EN, FR, DE, ES & NL

Assessing the Reliability of Complex Models Book Review:

Advances in computing hardware and algorithms have dramatically improved the ability to simulate complex processes computationally. Today's simulation capabilities offer the prospect of addressing questions that in the past could be addressed only by resource-intensive experimentation, if at all. Assessing the Reliability of Complex Models recognizes the ubiquity of uncertainty in computational estimates of reality and the necessity for its quantification. As computational science and engineering have matured, the process of quantifying or bounding uncertainties in a computational estimate of a physical quality of interest has evolved into a small set of interdependent tasks: verification, validation, and uncertainty of quantification (VVUQ). In recognition of the increasing importance of computational simulation and the increasing need to assess uncertainties in computational results, the National Research Council was asked to study the mathematical foundations of VVUQ and to recommend steps that will ultimately lead to improved processes. Assessing the Reliability of Complex Models discusses changes in education of professionals and dissemination of information that should enhance the ability of future VVUQ practitioners to improve and properly apply VVUQ methodologies to difficult problems, enhance the ability of VVUQ customers to understand VVUQ results and use them to make informed decisions, and enhance the ability of all VVUQ stakeholders to communicate with each other. This report is an essential resource for all decision and policy makers in the field, students, stakeholders, UQ experts, and VVUQ educators and practitioners.

High Performance Computing Applications in Numerical Simulation and Edge Computing

High Performance Computing Applications in Numerical Simulation and Edge Computing
Author: Changjun Hu,Wen Yang,Congfeng Jiang,Dong Dai
Publsiher: Springer Nature
Total Pages: 247
Release: 2019-08-28
ISBN 10: 9813299878
ISBN 13: 9789813299870
Language: EN, FR, DE, ES & NL

High Performance Computing Applications in Numerical Simulation and Edge Computing Book Review:

This book constitutes the referred proceedings of two workshops held at the 32nd ACM International Conference on Supercomputing, ACM ICS 2018, in Beijing, China, in June 2018. This volume presents the papers that have been accepted for the following workshops: Second International Workshop on High Performance Computing for Advanced Modeling and Simulation in Nuclear Energy and Environmental Science, HPCMS 2018, and First International Workshop on HPC Supported Data Analytics for Edge Computing, HiDEC 2018. The 20 full papers presented during HPCMS 2018 and HiDEC 2018 were carefully reviewed and selected from numerous submissions. The papers reflect such topics as computing methodologies; parallel algorithms; simulation types and techniques; machine learning.

Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes
Author: Jun Wang,Xin Li,Chris Allison,Judy Hohorst
Publsiher: Woodhead Publishing
Total Pages: 608
Release: 2020-11-10
ISBN 10: 0128181915
ISBN 13: 9780128181911
Language: EN, FR, DE, ES & NL

Nuclear Power Plant Design and Analysis Codes Book Review:

Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe. Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting.

Computational Science ICCS 2020

Computational Science   ICCS 2020
Author: Valeria V. Krzhizhanovskaya,Gábor Závodszky,Michael H. Lees,Jack J. Dongarra,Peter M. A. Sloot,Sérgio Brissos,João Teixeira
Publsiher: Springer Nature
Total Pages: 667
Release: 2020
ISBN 10: 3030504336
ISBN 13: 9783030504335
Language: EN, FR, DE, ES & NL

Computational Science ICCS 2020 Book Review:

The seven-volume set LNCS 12137, 12138, 12139, 12140, 12141, 12142, and 12143 constitutes the proceedings of the 20th International Conference on Computational Science, ICCS 2020, held in Amsterdam, The Netherlands, in June 2020.* The total of 101 papers and 248 workshop papers presented in this book set were carefully reviewed and selected from 719 submissions (230 submissions to the main track and 489 submissions to the workshops). The papers were organized in topical sections named: Part I: ICCS Main Track Part II: ICCS Main Track Part III: Advances in High-Performance Computational Earth Sciences: Applications and Frameworks; Agent-Based Simulations, Adaptive Algorithms and Solvers; Applications of Computational Methods in Artificial Intelligence and Machine Learning; Biomedical and Bioinformatics Challenges for Computer Science Part IV: Classifier Learning from Difficult Data; Complex Social Systems through the Lens of Computational Science; Computational Health; Computational Methods for Emerging Problems in (Dis-)Information Analysis Part V: Computational Optimization, Modelling and Simulation; Computational Science in IoT and Smart Systems; Computer Graphics, Image Processing and Artificial Intelligence Part VI: Data Driven Computational Sciences; Machine Learning and Data Assimilation for Dynamical Systems; Meshfree Methods in Computational Sciences; Multiscale Modelling and Simulation; Quantum Computing Workshop Part VII: Simulations of Flow and Transport: Modeling, Algorithms and Computation; Smart Systems: Bringing Together Computer Vision, Sensor Networks and Machine Learning; Software Engineering for Computational Science; Solving Problems with Uncertainties; Teaching Computational Science; UNcErtainty QUantIficatiOn for ComputationAl modeLs *The conference was canceled due to the COVID-19 pandemic.

Towards a Supported Common NEAMS Software Stack

Towards a Supported Common NEAMS Software Stack
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2012
ISBN 10: 1928374650XXX
ISBN 13: OCLC:967923377
Language: EN, FR, DE, ES & NL

Towards a Supported Common NEAMS Software Stack Book Review:

The NEAMS IPSC's are developing multidimensional, multiphysics, multiscale simulation codes based on first principles that will be capable of predicting all aspects of current and future nuclear reactor systems. These new breeds of simulation codes will include rigorous verification, validation and uncertainty quantification checks to quantify the accuracy and quality of the simulation results. The resulting NEAMS IPSC simulation codes will be an invaluable tool in designing the next generation of Nuclear Reactors and also contribute to a more speedy process in the acquisition of licenses from the NRC for new Reactor designs. Due to the high resolution of the models, the complexity of the physics and the added computational resources to quantify the accuracy/quality of the results, the NEAMS IPSC codes will require large HPC resources to carry out the production simulation runs.

Energy and Water Development Appropriations for 2001 Department of Energy

Energy and Water Development Appropriations for 2001  Department of Energy
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2000
ISBN 10: 1928374650XXX
ISBN 13: SRLF:AA0010258549
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2001 Department of Energy Book Review:

Energy and Water Development Appropriations for 2001

Energy and Water Development Appropriations for 2001
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2000
ISBN 10: 1928374650XXX
ISBN 13: UCBK:C072279309
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2001 Book Review:

106 2 Hearings Energy And Water Development Appropriations For 2001 Part 6 March 21 2000

106 2 Hearings  Energy And Water Development Appropriations For 2001  Part 6  March 21  2000
Author: Anonim
Publsiher: Unknown
Total Pages: 135
Release: 2000
ISBN 10: 1928374650XXX
ISBN 13: STANFORD:36105050149116
Language: EN, FR, DE, ES & NL

106 2 Hearings Energy And Water Development Appropriations For 2001 Part 6 March 21 2000 Book Review:

IAEA Coordinated Research Project on HTGR Reactor Physics Thermal hydraulics and Depletion Uncertainty Analysis

IAEA Coordinated Research Project on HTGR Reactor Physics  Thermal hydraulics and Depletion Uncertainty Analysis
Author: Anonim
Publsiher: Unknown
Total Pages: 68
Release: 2015
ISBN 10: 1928374650XXX
ISBN 13: OCLC:946824193
Language: EN, FR, DE, ES & NL

IAEA Coordinated Research Project on HTGR Reactor Physics Thermal hydraulics and Depletion Uncertainty Analysis Book Review:

The continued development of High Temperature Gas Cooled Reactors (HTGRs) requires verification of HTGR design and safety features with reliable high fidelity physics models and robust, efficient, and accurate codes. The predictive capability of coupled neutronics/thermal-hydraulics and depletion simulations for reactor design and safety analysis can be assessed with sensitivity analysis (SA) and uncertainty analysis (UA) methods. Uncertainty originates from errors in physical data, manufacturing uncertainties, modelling and computational algorithms. (The interested reader is referred to the large body of published SA and UA literature for a more complete overview of the various types of uncertainties, methodologies and results obtained). SA is helpful for ranking the various sources of uncertainty and error in the results of core analyses. SA and UA are required to address cost, safety, and licensing needs and should be applied to all aspects of reactor multi-physics simulation. SA and UA can guide experimental, modelling, and algorithm research and development. Current SA and UA rely either on derivative-based methods such as stochastic sampling methods or on generalized perturbation theory to obtain sensitivity coefficients. Neither approach addresses all needs. In order to benefit from recent advances in modelling and simulation and the availability of new covariance data (nuclear data uncertainties) extensive sensitivity and uncertainty studies are needed for quantification of the impact of different sources of uncertainties on the design and safety parameters of HTGRs. Only a parallel effort in advanced simulation and in nuclear data improvement will be able to provide designers with more robust and well validated calculation tools to meet design target accuracies. In February 2009, the Technical Working Group on Gas-Cooled Reactors (TWG-GCR) of the International Atomic Energy Agency (IAEA) recommended that the proposed Coordinated Research Program (CRP) on the HTGR Uncertainty Analysis in Modelling (UAM) be implemented. This CRP is a continuation of the previous IAEA and Organization for Economic Co-operation and Development (OECD)/Nuclear Energy Agency (NEA) international activities on Verification and Validation (V & V) of available analytical capabilities for HTGR simulation for design and safety evaluations [1], [2], [3]. Within the framework of these activities different numerical and experimental benchmark problems were performed and insight was gained about specific physics phenomena and the adequacy of analysis methods.

Energy and Water Development Appropriations for 2010

Energy and Water Development Appropriations for 2010
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2009
ISBN 10: 1928374650XXX
ISBN 13: MINN:31951D031238772
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2010 Book Review:

Energy and Water Development Appropriations for 2014 Department of Energy fiscal year 2014 justifications

Energy and Water Development Appropriations for 2014  Department of Energy fiscal year 2014 justifications
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2013
ISBN 10: 1928374650XXX
ISBN 13: STANFORD:36105050648463
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2014 Department of Energy fiscal year 2014 justifications Book Review:

Energy and Water Development Appropriations for 2012 Dept of Energy FY 2012 justifications cont

Energy and Water Development Appropriations for 2012  Dept  of Energy FY 2012 justifications  cont
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2011
ISBN 10: 1928374650XXX
ISBN 13: UCR:31210023152513
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2012 Dept of Energy FY 2012 justifications cont Book Review:

Energy and Water Development Appropriations for 2008

Energy and Water Development Appropriations for 2008
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2007
ISBN 10: 1928374650XXX
ISBN 13: STANFORD:36105050446744
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2008 Book Review:

Energy and Water Development Appropriations for 2008 Dept of Energy FY 2008 budget justifications budget highlights NNSA other defense activities

Energy and Water Development Appropriations for 2008  Dept  of Energy FY 2008 budget justifications  budget highlights  NNSA  other defense activities
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 135
Release: 2007
ISBN 10: 1928374650XXX
ISBN 13: UCBK:C095118556
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2008 Dept of Energy FY 2008 budget justifications budget highlights NNSA other defense activities Book Review:

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors
Author: Ferry Roelofs
Publsiher: Woodhead Publishing
Total Pages: 462
Release: 2018-11-30
ISBN 10: 0081019815
ISBN 13: 9780081019818
Language: EN, FR, DE, ES & NL

Thermal Hydraulics Aspects of Liquid Metal Cooled Nuclear Reactors Book Review:

Thermal Hydraulics Aspects of Liquid Metal cooled Nuclear Reactors is a comprehensive collection of liquid metal thermal hydraulics research and development for nuclear liquid metal reactor applications. A deliverable of the SESAME H2020 project, this book is written by top European experts who discuss topics of note that are supplemented by an international contribution from U.S. partners within the framework of the NEAMS program under the U.S. DOE. This book is a convenient source for students, professionals and academics interested in liquid metal thermal hydraulics in nuclear applications. In addition, it will also help newcomers become familiar with current techniques and knowledge. Presents the latest information on one of the deliverables of the SESAME H2020 project Provides an overview on the design and history of liquid metal cooled fast reactors worldwide Describes the challenges in thermal hydraulics related to the design and safety analysis of liquid metal cooled fast reactors Includes the codes, methods, correlations, guidelines and limitations for liquid metal fast reactor thermal hydraulic simulations clearly Discusses state-of-the-art, multi-scale techniques for liquid metal fast reactor thermal hydraulics applications