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Status Report On High Fidelity Reactor Simulation
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Book Synopsis Status Report on High Fidelity Reactor Simulation by : B. Smith
Download or read book Status Report on High Fidelity Reactor Simulation written by B. Smith and published by . This book was released on 2006 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report presents the effort under way at Argonne National Laboratory toward a comprehensive, integrated computational tool intended mainly for the high-fidelity simulation of sodium-cooled fast reactors. The main activities carried out involved neutronics, thermal hydraulics, coupling strategies, software architecture, and high-performance computing. A new neutronics code, UNIC, is being developed. The first phase involves the application of a spherical harmonics method to a general, unstructured three-dimensional mesh. The method also has been interfaced with a method of characteristics. The spherical harmonics equations were implemented in a stand-alone code that was then used to solve several benchmark problems. For thermal hydraulics, a computational fluid dynamics code called Nek5000, developed in the Mathematics and Computer Science Division for coupled hydrodynamics and heat transfer, has been applied to a single-pin, periodic cell in the wire-wrap geometry typical of advanced burner reactors. Numerical strategies for multiphysics coupling have been considered and higher-accuracy efficient methods proposed to finely simulate coupled neutronic/thermal-hydraulic reactor transients. Initial steps have been taken in order to couple UNIC and Nek5000, and simplified problems have been defined and solved for testing. Furthermore, we have begun developing a lightweight computational framework, based in part on carefully selected open source tools, to nonobtrusively and efficiently integrate the individual physics modules into a unified simulation tool.
Book Synopsis Status Report on Multigroup Cross Section Generation Code Development for High-fidelity Deterministic Neutronics Simulation System by :
Download or read book Status Report on Multigroup Cross Section Generation Code Development for High-fidelity Deterministic Neutronics Simulation System written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Under the fast reactor simulation program launched in April 2007, development of an advanced multigroup cross section generation code was initiated in July 2007, in conjunction with the development of the high-fidelity deterministic neutron transport code UNIC. The general objectives are to simplify the existing multi-step schemes and to improve the resolved and unresolved resonance treatments. Based on the review results of current methods and the fact that they have been applied successfully to fast critical experiment analyses and fast reactor designs for last three decades, the methodologies of the ETOE-2/MC2−2SDX code system were selected as the starting set of methodologies for multigroup cross section generation for fast reactor analysis. As the first step for coupling with the UNIC code and use in a parallel computing environment, the MC2-2 code was updated by modernizing the memory structure and replacing old data management package subroutines and functions with FORTRAN 90 based routines. Various modifications were also made in the ETOE-2 and MC2-2 codes to process the ENDF/B-VII.0 data properly. Using the updated ETOE-2/MC2-2 code system, the ENDF/B-VII.0 data was successfully processed for major heavy and intermediate nuclides employed in sodium-cooled fast reactors. Initial verification tests of the MC2-2 libraries generated from ENDF/B-VII.0 data were performed by inter-comparison of twenty-one group infinite dilute total cross sections obtained from MC2-2, VIM, and NJOY. For almost all nuclides considered, MC2-2 cross sections agreed very well with those from VIM and NJOY. Preliminary validation tests of the ENDF/B-VII.0 libraries of MC2-2 were also performed using a set of sixteen fast critical benchmark problems. The deterministic results based on MC2−2TWODANT calculations were in good agreement with MCNP solutions within ≈0.25% [Delta][rho], except a few small LANL fast assemblies. Relative to the MCNP solution, the MC2−2TWODANT results overestimated the multiplication factor by 0.22 ≈ 0.35% [Delta][rho] for these small systems with very hard neutron spectrum. Comparisons of measured and calculated values for the fission reaction rate ratios of Godiva and Jezebel assemblies also showed that the MC2−2TWODANT results agreed well with measurements within 2.7%. From a series of methodology review and ENDF/B-VII.0 data processing, several improvement needs to enhance accuracy were also identified for the ETOE-2/MC2-2 code system, including the multigroup slowing-down solution for whole-energy range, proper treatment for anisotropy of inelastic scattering, improved evaluation of inelastic and high-order anisotropic scattering source in RABANL calculations.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Advanced Modeling and Simulation of Nuclear Reactors by : Jingang Liang
Download or read book Advanced Modeling and Simulation of Nuclear Reactors written by Jingang Liang and published by Frontiers Media SA. This book was released on 2023-04-10 with total page 161 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Integral Fast Reactor Program Quarterly Progress Report for the Period July-September 1993 by :
Download or read book Integral Fast Reactor Program Quarterly Progress Report for the Period July-September 1993 written by and published by . This book was released on 1993 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Nuclear Materials by : Pavel V. Tsvetkov
Download or read book Nuclear Materials written by Pavel V. Tsvetkov and published by BoD – Books on Demand. This book was released on 2021-04 with total page 151 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book examines nuclear materials through select chapters focusing on the impact of reactor technology, use of materials data in modeling applications, and reasoning in design choices. It provides an opportunity to explore contemporary and emerging frontiers. Chapters cover such topics as manufacturing approaches, forms, fundamental considerations, and applications as well as highlight contemporary pathways in nuclear material development.
Book Synopsis Fast Spectrum Reactors by : Alan E. Waltar
Download or read book Fast Spectrum Reactors written by Alan E. Waltar and published by Springer Science & Business Media. This book was released on 2011-09-28 with total page 717 pages. Available in PDF, EPUB and Kindle. Book excerpt: This book is a complete update of the classic 1981 FAST BREEDER REACTORS textbook authored by Alan E. Waltar and Albert B. Reynolds, which , along with the Russian translation, served as a major reference book for fast reactors systems. Major updates include transmutation physics (a key technology to substantially ameliorate issues associated with the storage of high-level nuclear waste ), advances in fuels and materials technology (including metal fuels and cladding materials capable of high-temperature and high burnup), and new approaches to reactor safety (including passive safety technology), New chapters on gas-cooled and lead-cooled fast spectrum reactors are also included. Key international experts contributing to the text include Chaim Braun, (Stanford University) Ronald Omberg, (Pacific Northwest National Laboratory, Massimo Salvatores (CEA, France), Baldev Raj, (Indira Gandhi Center for Atomic Research, India) , John Sackett (Argonne National Laboratory), Kevan Weaver, (TerraPower Corporation) ,James Seinicki(Argonne National Laboratory). Russell Stachowski (General Electric), Toshikazu Takeda (University of Fukui, Japan), and Yoshitaka Chikazawa (Japan Atomic Energy Agency).
Book Synopsis Global Progress on Molten Salt Reactors by : Thomas James Dolan
Download or read book Global Progress on Molten Salt Reactors written by Thomas James Dolan and published by Elsevier. This book was released on 2024-02-05 with total page 294 pages. Available in PDF, EPUB and Kindle. Book excerpt: Global Progress on Molten Salt Reactors: A Companion to Dolan’s Molten Salt Reactors and Thorium Energy, Second Edition presents global perspectives on the latest research and technological advances. Each case study utilizes a comprehensive template that guides the reader through country specific research. Useful data which can be applied to work and research is included, along with a list of references for further research. Researchers, professional engineers and policymakers will gain a broad picture of worldwide MSR activity and a deep understanding of how theory and practical guidance is applied in a variety of settings, including budgets, approaches and constraints. Provides a collection of case studies from 23 countries, presenting their latest research and activities on Molten Salt Reactors Based on chapter 26 of the first edition of Dolan’s Molten Salt Reactors and Thorium Energy, this companion title presents expanded and more complete coverage of global activities and research Includes advanced technologies, reactor designs and safety and management strategies
Book Synopsis Advanced High-Fidelity Reactor Simulators Based on Neutron Transport and Subchannel Methodologies by : Miriam Knebel
Download or read book Advanced High-Fidelity Reactor Simulators Based on Neutron Transport and Subchannel Methodologies written by Miriam Knebel and published by . This book was released on 2017 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High-Performance Computing Applications in Numerical Simulation and Edge Computing by : Changjun Hu
Download or read book High-Performance Computing Applications in Numerical Simulation and Edge Computing written by Changjun Hu and published by Springer Nature. This book was released on 2019-08-28 with total page 247 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.
Book Synopsis Nuclear Power Plant Design and Analysis Codes by : Jun Wang
Download or read book Nuclear Power Plant Design and Analysis Codes written by Jun Wang and published by Woodhead Publishing. This book was released on 2020-11-10 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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
Book Synopsis Preparing for the High Frontier by : National Research Council
Download or read book Preparing for the High Frontier written by National Research Council and published by National Academies Press. This book was released on 2011-12-09 with total page 114 pages. Available in PDF, EPUB and Kindle. Book excerpt: As the National Aeronautics and Space Administration (NASA) retires the Space Shuttle and shifts involvement in International Space Station (ISS) operations, changes in the role and requirements of NASA's Astronaut Corps will take place. At the request of NASA, the National Research Council (NRC) addressed three main questions about these changes: what should be the role and size of Johnson Space Center's (JSC) Flight Crew Operations Directorate (FCOD); what will be the requirements of astronaut training facilities; and is the Astronaut Corps' fleet of training aircraft a cost-effective means of preparing astronauts for NASA's spaceflight program? This report presents an assessment of several issues driven by these questions. This report does not address explicitly the future of human spaceflight.
Book Synopsis Coupled High Fidelity Thermal Hydraulics and Neutronics for Reactor Safety Simulations by :
Download or read book Coupled High Fidelity Thermal Hydraulics and Neutronics for Reactor Safety Simulations written by and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the un'SCRAM'ed reactor transitions from forced to free convection (Natural circulation). Results will be presented that show the difference that the first order in time truncation physics makes on the transient. The purpose of this document is to illuminate a possible problem in traditional reactor simulation approaches. Detailed studies need to be done on each simulation code for each transient analyzed to determine if the first order truncation physics plays an important role.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1988 with total page 974 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Commerce Business Daily written by and published by . This book was released on 1999-05 with total page 1974 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Progress Report for Fuel Cells for Transportation by :
Download or read book Progress Report for Fuel Cells for Transportation written by and published by DIANE Publishing. This book was released on with total page 153 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High Fidelity Simulation of Buoyancy-driven Fluid Flow in Flouride Salt-cooled High Temperature Reactors Using the Spectral Element Method by : Tri Nguyen
Download or read book High Fidelity Simulation of Buoyancy-driven Fluid Flow in Flouride Salt-cooled High Temperature Reactors Using the Spectral Element Method written by Tri Nguyen and published by . This book was released on 2023 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: The world transition from fossil to clean energy is challenging given that fossil fuels still contribute the most of world energy demand. While renewable energy cannot displace fossil fuels from the electricity mix, nuclear energy is the leading solution for the world energy transition mission. Among advanced nuclear reactor designs, Fluoride salt-cooled high-temperature reactors (FHRs) are considered to have the greatest inherent safety thanks to Molten salts' special thermophysical and neutronic properties. This research investigates buoyancy-driven flow in particular aspects that play a crucial role in the passive safety of advanced FHRs. These aspects include the natural circulation system (NCS), the downcomer, and the reactor core. The GPU-based high-fidelity high-order spectral element code NekRS is used to perform all simulations. First, the simplest possible NCS -- thermosiphons have been investigated by a series of Large Eddy Simulation (LES) for a wide range of Rayleigh and Lt/D ratios, where Lt is the total length of the loop, and D is the pipe diameters. The simulation results demonstrate a capability to design thermosiphon loops with the prospect of Kairos Power FHR (KP-FHR) design. Then, Direct Numerical Simulation (DNS) of mixed convection in the downcomer for a wide range of Reynolds, Prandtl, and Richardson numbers was performed following the inputs from Kairos Power. An unprecedented high-fidelity numerical DNS database has been established, and new correlations for mixed convection in the downcomer of FHR with molten salt FLiBe are proposed. The newly proposed correlations could predict the trend of the Nusselt number dataset in the heat transfer deterioration region within +/- 10% of the DNS data confidence interval, which is a considerable improvement compared to all other available correlations in the literature. The generated downcomer DNS database will also help better understand Reynolds-averaged Navier--Stokes (RANS) model performance and physical explanation for turbulence model shortcomings. Finally, we perform a full-core high-fidelity LES with the consideration of the FLiBe variables properties for the test reactor "Hermes" of KP-FHR design. The heat transfer data has been obtained and compared with existing correlations in the literature. A good agreement has been achieved between NekRS results and correlations, providing confidence in the generated data. The Nusselt number calculation results could highlight the potential issues of using the existing correlations and propose the correlation implementation depending on the operational regimes of FHRs. Overall, the high-fidelity data and new correlations have implications for the design and optimization of FHRs, providing valuable insights into flow stability, turbulence characteristics, and heat transfer performance.
