Download or read book Effective Spatial Mapping for Coupled Code Analysis of Thermal hydraulics neutron kinetics of Boiling Water Reactors written by and published by . This book was released on 2013 with total page 148 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Modelling of Nuclear Reactor Multi physics written by Christophe Demazière and published by Academic Press. This book was released on 2019-11-19 with total page 370 pages. Available in PDF, EPUB and Kindle. Book excerpt: Modelling of Nuclear Reactor Multiphysics: From Local Balance Equations to Macroscopic Models in Neutronics and Thermal-Hydraulics is an accessible guide to the advanced methods used to model nuclear reactor systems. The book addresses the frontier discipline of neutronic/thermal-hydraulic modelling of nuclear reactor cores, presenting the main techniques in a generic manner and for practical reactor calculations.The modelling of nuclear reactor systems is one of the most challenging tasks in complex system modelling, due to the many different scales and intertwined physical phenomena involved. The nuclear industry as well as the research institutes and universities heavily rely on the use of complex numerical codes. All the commercial codes are based on using different numerical tools for resolving the various physical fields, and to some extent the different scales, whereas the latest research platforms attempt to adopt a more integrated approach in resolving multiple scales and fields of physics. The book presents the main algorithms used in such codes for neutronic and thermal-hydraulic modelling, providing the details of the underlying methods, together with their assumptions and limitations. Because of the rapidly expanding use of coupled calculations for performing safety analyses, the analysists should be equally knowledgeable in all fields (i.e. neutron transport, fluid dynamics, heat transfer).The first chapter introduces the book's subject matter and explains how to use its digital resources and interactive features. The following chapter derives the governing equations for neutron transport, fluid transport, and heat transfer, so that readers not familiar with any of these fields can comprehend the book without difficulty. The book thereafter examines the peculiarities of nuclear reactor systems and provides an overview of the relevant modelling strategies. Computational methods for neutron transport, first at the cell and assembly levels, then at the core level, and for one-/two-phase flow transport and heat transfer are treated in depth in respective chapters. The coupling between neutron transport solvers and thermal-hydraulic solvers for coarse mesh macroscopic models is given particular attention in a dedicated chapter. The final chapter summarizes the main techniques presented in the book and their interrelation, then explores beyond state-of-the-art modelling techniques relying on more integrated approaches. - Covers neutron transport, fluid dynamics, and heat transfer, and their interdependence, in one reference - Analyses the emerging area of multi-physics and multi-scale reactor modelling - Contains 71 short videos explaining the key concepts and 77 interactive quizzes allowing the readers to test their understanding
Download or read book Qualification of Spatial Coupling of System Reactor Simulators for BWR Stability written by Elsa de Alfonso Prieto-Puga and published by . This book was released on 2008 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Boiling Water Reactor (BWR) stability is a very complex and relevant issue in nuclear reactor safety, as well as a challenge for current simulation codes. The presence of reactivity unstabilities in the core requires the thermal-hydraulics (TH) codes to be coupled with full three dimensional neutron kinetics (NK) core models. The spatial description of the reactor core is different for TH and NK models. Usually TH code uses fewer channels to represent the core, whereas NK code uses one explicit node for each fuel assembly. Therefore, a spatial mapping of coarse grid TH and fine grid NK domain is necessary. It is well-known that a simpler TH model will significantly reduce the computational time. However, improper mappings may result in loss of valuable information, thus causing inaccurate prediction of safety parameters. The purpose of this work is to study the possibilities of spatial coupling and develop recommendations for NK-TH mapping for simulating unstability transients. In this work, control rod perturbation (CRP) transient is performed with coupled codes TRACE/PARCS for Ringhals-1 Cycle 14 to determine decay ratio (DR) and natural frequency (NF) using several spatial coupling. The effectiveness and accuracy of predicted DR and NF are compared to a reference case of 325 thermo-hydraulic channels (THC). A model with a 5 THC grouped according to assembly position and radial power show fairly accurate results, with a range of discrepancies of the same order as the reference case, and more than 10 times less computational time.
Download or read book A Generalized Interface Module for the Coupling of Spatial Kinetics and Thermal hydraulics Codes written by and published by . This book was released on 1999 with total page 23 pages. Available in PDF, EPUB and Kindle. Book excerpt: A generalized interface module has been developed for the coupling of any thermal-hydraulics code to any spatial kinetics code. The coupling scheme was designed and implemented with emphasis placed on maximizing flexibility while minimizing modifications to the respective codes. In this design, the thermal-hydraulics, general interface, and spatial kinetics codes function independently and utilize the Parallel Virtual Machine software to manage cross-process communication. Using this interface, the USNRC version of the 3D neutron kinetics code, PARCX, has been coupled to the USNRC system analysis codes RELAP5 and TRAC-M. RELAP5/PARCS assessment results are presented for two NEACRP rod ejection benchmark problems and an NEA/OECD main steam line break benchmark problem. The assessment of TRAC-M/PARCS has only recently been initiated, nonetheless, the capabilities of the coupled code are presented for a typical PWR system/core model.
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1988 with total page 268 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Energy Research Abstracts written by and published by . This book was released on 1991-10 with total page 582 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Light water reactor Coupled Neutronic and Thermal hydraulic Codes written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An overview is presented of computer codes that model light water reactor cores with coupled neutronics and thermal-hydraulics. This includes codes for transient analysis and codes for steady state analysis which include fuel depletion and fission product buildup. Applications in nuclear design, reactor operations and safety analysis are given and the major codes in use in the USA are identified. The neutronic and thermal-hydraulic methodologies and other code features are outlined for three steady state codes (PDQ7, NODE-P/B and SIMULATE) and four dynamic codes (BNL-TWIGL, MEKIN, RAMONA-3B, RETRAN-02). Speculation as to future trends with such codes is also presented.
Download or read book RAMONA 3B written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The modification and interfacing of two computer codes, RAMONA-3B and MINET, for the thermal hydraulic transient analysis of a Boiling Water Reactor nuclear steam supply system, is described. The RAMONA-3B code provides for multi-channel thermal hydraulics and three-dimensional (or one-dimensional) neutron kinetics analysis of a boiling water reactor core. The RAMONA-3B system representation terminates at the end of the steam line and at the junction of the feedwater line at the vessel inlet. By interfacing RAMONA-3B with MINET, a generic balance-of-plant systems analysis code, a complete BWR systems code with detailed core modeling was obtained. The result is a code of particular importance to the analysis of transients such as ATWS. A comparison between the 3-D and 1-D neutronics representation is provided, along with a test case utilizing the composite RAMONA-3B/MINET code.
Download or read book Use and Development of Coupled Computer Codes for the Analysis of Accidents at Nuclear Power Plants written by International Atomic Energy Agency and published by . This book was released on 2007 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt: This publication summarizes the results of the Technical Meeting on "Progress in development and use of coupled codes for accident analysis". The significantly increased capacity of new computation technology has made it possible to proceed the code coupling not only between neutronics and thermal hydraulics but also between thermal hydraulics and one or more other disciplines. This publication contains a review of state-of-the-art technologies in code coupling and its application to the accident analysis of nuclear power plants. The presentations and the papers given at the Technical Meeting are enclosed on the attached CD.--Publisher's description.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 1174 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book TITAN written by D. P. Griggs and published by . This book was released on 1984 with total page 505 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Overview of Coupled System Thermal hydraulic 3D Neutron Kinetic Code Applications written by Anis Bousbia Salah (t.d.-) and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book BEACON MOD3 written by and published by . This book was released on 1980 with total page 296 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Tightly Coupled Neutronics and Thermal hydraulics Using Open source Software written by and published by . This book was released on 2013 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Coupling Between Monte Carlo Neutron Transport and Thermal hydraulics for the Simulation of Transients Due to Reactivity Insertions written by Margaux Faucher and published by . This book was released on 2019 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of the main issues for the study of a reactor behaviour is to model the propagation of the neutrons, described by the Boltzmann transport equation, in the presence of multi-physics phenomena, such as the coupling between neutron transport, thermal-hydraulics and thermomecanics. Thanks to the growing computer power, it is now feasible to apply Monte Carlo methods to the solution of non-stationary transport problems in reactor physics, which play an instrumental role in producing reference numerical solutions for the analysis of transients occurring during normal and accidental behaviour.The goal of this Ph. D. thesis is to develop, verify and test a coupling scheme between the Monte Carlo code TRIPOLI-4 and thermal-hydraulics, so as to provide a reference tool for the simulation of reactivity-induced transients in PWRs.We have first tested the kinetic capabilities of TRIPOLI-4 (i.e., time dependent without thermal-hydraulics feedback), evaluating the different existing methods and implementing new techniques. Then, we have developed a multi-physics interface for TRIPOLI-4, and more specifically a coupling scheme between TRIPOLI-4 and the thermal-hydraulics sub-channel code SUBCHANFLOW. Finally, we have performed a preliminary analysis of the stability of the coupling scheme. Indeed, due to the stochastic nature of the outputs produced by TRIPOLI-4, uncertainties are inherent to our coupling scheme and propagate along the coupling iterations. Moreover, thermal-hydraulics equations are non linear, so the prediction of the propagation of the uncertainties is not straightforward.
Download or read book Introductory Nuclear Reactor Dynamics written by Karl Otto Ott and published by . This book was released on 1985 with total page 384 pages. Available in PDF, EPUB and Kindle. Book excerpt: This text presents the theory and methods of prediction that are the heart of nuclear reactor safety. Time-dependent reactor behavior is explained in both mathematical and physical terms. This book also explains the logic behind the working formulas and calculational methods for reactor transients and illustrates typical dynamic responses. The classical concept of point kinetics is developed in three steps, with discussion of various solutions to kinetics problems. Each chapter includes homework problems and review questions.
Download or read book Super Light Water Reactors and Super Fast Reactors written by Yoshiaki Oka and published by Springer Science & Business Media. This book was released on 2010-07-01 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt: Super Light Water Reactors and Super Fast Reactors provides an overview of the design and analysis of nuclear power reactors. Readers will gain the understanding of the conceptual design elements and specific analysis methods of supercritical-pressure light water cooled reactors. Nuclear fuel, reactor core, plant control, plant stand-up and stability are among the topics discussed, in addition to safety system and safety analysis parameters. Providing the fundamentals of reactor design criteria and analysis, this volume is a useful reference to engineers, industry professionals, and graduate students involved with nuclear engineering and energy technology.
