Reactor Physics Characteristics Of The High Temperature Reactor
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| Author | : Luigi Massimo |
| Publisher | : Elsevier |
| Total Pages | : 249 |
| Release | : 2013-10-22 |
| Genre | : Technology & Engineering |
| ISBN | : 1483280284 |
Physics of High-Temperature Reactors focuses on the physics of high-temperature reactors (HTRs) and covers topics ranging from fuel cycles and refueling strategies to neutron cross-sections, transport and diffusion theory, and resonance absorption. Spectrum calculations and cross-section averaging are also discussed, along with the temperature coefficient and reactor control. Comprised of 16 chapters, this book begins with a general description of the HTR core as well as its performance limitations. The next chapter deals with general considerations about HTR physics, including quantities to be determined and optimized in the design of nuclear reactors. Potential scattering and resonance reactions between neutrons and atomic nuclei are then considered, together with basic aspects of transport and diffusion theory. Subsequent chapters explore methods for solving the diffusion equation; slowing-down and neutron thermalization in graphite; HTR core design, fuel management, and cost calculations; and core dynamics and accident analysis. The final chapter describes the sequence of reactor design calculations. This monograph is written primarily for students of HTR physics who are preparing to enter the field as well as technologists of other disciplines who are working on the system.
| Author | : J. G. Tyror |
| Publisher | : |
| Total Pages | : 9 |
| Release | : 1971 |
| Genre | : |
| ISBN | : |
| Author | : R. H. S. Winterton |
| Publisher | : Pergamon |
| Total Pages | : 212 |
| Release | : 1981 |
| Genre | : Science |
| ISBN | : |
Of reactor physics -- Reactor systems -- Fuel-road design -- Forced-convection heat transfer -- Boiling heat transfer -- Fluid flow -- Safety analysis -- Core thermohydraulic design -- Steam cycles -- Fusion reactors -- Temperature distribution following sudden total loss of cooling -- Properties of coolants -- Conversion factors -- Answers to selected problems.
| Author | : P. Mohanakrishnan |
| Publisher | : Elsevier |
| Total Pages | : 786 |
| Release | : 2021-05-19 |
| Genre | : Science |
| ISBN | : 012822441X |
Physics of Nuclear Reactors presents a comprehensive analysis of nuclear reactor physics. Editors P. Mohanakrishnan, Om Pal Singh, and Kannan Umasankari and a team of expert contributors combine their knowledge to guide the reader through a toolkit of methods for solving transport equations, understanding the physics of reactor design principles, and developing reactor safety strategies. The inclusion of experimental and operational reactor physics makes this a unique reference for those working and researching nuclear power and the fuel cycle in existing power generation sites and experimental facilities. The book also includes radiation physics, shielding techniques and an analysis of shield design, neutron monitoring and core operations. Those involved in the development and operation of nuclear reactors and the fuel cycle will gain a thorough understanding of all elements of nuclear reactor physics, thus enabling them to apply the analysis and solution methods provided to their own work and research. This book looks to future reactors in development and analyzes their status and challenges before providing possible worked-through solutions. Cover image: Kaiga Atomic Power Station Units 1 - 4, Karnataka, India. In 2018, Unit 1 of the Kaiga Station surpassed the world record of continuous operation, at 962 days. Image courtesy of DAE, India. Includes methods for solving neutron transport problems, nuclear cross-section data and solutions of transport theory Dedicates a chapter to reactor safety that covers mitigation, probabilistic safety assessment and uncertainty analysis Covers experimental and operational physics with details on noise analysis and failed fuel detection
| Author | : J. G. Tyror |
| Publisher | : Elsevier |
| Total Pages | : 194 |
| Release | : 2013-10-22 |
| Genre | : Technology & Engineering |
| ISBN | : 1483148920 |
An Introduction to the Neutron Kinetics of Nuclear Power Reactors introduces the reader to the neutron kinetics of nuclear power reactors. Topics covered include the neutron physics of reactor kinetics, feedback effects, water-moderated reactors, fast reactors, and methods of plant control. The reactor transients following faults are also discussed, along with the use of computers in the study of power reactor kinetics. This book is comprised of eight chapters and begins with an overview of the reactor physics characteristics of a nuclear power reactor and their influence on system design and operation. The use of a mathematical model of the system to study reactor kinetics and control is described. The following chapters explore the neutronic aspects of reactor kinetics; the interaction between neutronic events and the behavior of other physical quantities of the reactor; the influence of feedback effects on neutron kinetics; and the neutron kinetics of water-moderated reactors and fast reactors. The different control schemes for nuclear power reactors are also considered. The final chapter looks at the use of computers to solve the equations of kinetic models for nuclear power reactors. This monograph will be a useful resource for nuclear scientists, physicists, and engineers.
| Author | : Ioan Ursu |
| Publisher | : Elsevier |
| Total Pages | : 541 |
| Release | : 2015-08-03 |
| Genre | : Technology & Engineering |
| ISBN | : 1483150577 |
Physics and Technology of Nuclear Materials presents basic information regarding the structure, properties, processing methods, and response to irradiation of the key materials that fission and fusion nuclear reactors have to rely upon. Organized into 12 chapters, this book begins with selectively several fundamentals of nuclear physics. Subsequent chapters focus on the nuclear materials science; nuclear fuel; structural materials; moderator materials employed to ""slow down"" fission neutrons; and neutron highly absorbent materials that serve in reactor's power control. Other chapters explore the cooling agents; fluids carrying the energy to its final stage of conversion into electric power; thermal and biological shielding materials; some outstanding reactor components; and irradiated fuel reprocessing. The last two chapters deal with nuclear material quality inspection by destructive and non-destructive methods, and specific materials envisaged for use in future thermonuclear reactors. This monograph will be helpful for a wide range of specialists wishing to gear their research and development, education, and other activities toward the field of nuclear power and nuclear technology.
| Author | : Elmer E. Lewis |
| Publisher | : Elsevier |
| Total Pages | : 311 |
| Release | : 2008-01-18 |
| Genre | : Technology & Engineering |
| ISBN | : 0080560431 |
Fundamentals of Nuclear Reactor Physics offers a one-semester treatment of the essentials of how the fission nuclear reactor works, the various approaches to the design of reactors, and their safe and efficient operation . It provides a clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release. It provides in-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution. It includes ample worked-out examples and over 100 end-of-chapter problems. Engineering students will find this applications-oriented approach, with many worked-out examples, more accessible and more meaningful as they aspire to become future nuclear engineers. - A clear, general overview of atomic physics from the standpoint of reactor functionality and design, including the sequence of fission reactions and their energy release - In-depth discussion of neutron reactions, including neutron kinetics and the neutron energy spectrum, as well as neutron spatial distribution - Ample worked-out examples and over 100 end-of-chapter problems - Full Solutions Manual
| Author | : Shengyao Jiang |
| Publisher | : Springer Nature |
| Total Pages | : 510 |
| Release | : 2020-11-19 |
| Genre | : Science |
| ISBN | : 9811595658 |
This book introduces readers to gas flows and heat transfer in pebble bed reactor cores. It addresses fundamental issues regarding experimental and modeling methods for complex multiphase systems, as well as relevant applications and recent research advances. The numerical methods and experimental measurements/techniques used to solve pebble flows, as well as the content on radiation modeling for high-temperature pebble beds, will be of particular interest. This book is intended for a broad readership, including researchers and practitioners, and is sure to become a key reference resource for students and professionals alike.
| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 639 |
| Release | : 2012-06 |
| Genre | : Business & Economics |
| ISBN | : 9789201253101 |
This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.
| Author | : |
| Publisher | : |
| Total Pages | : |
| Release | : 2010 |
| Genre | : |
| ISBN | : |
Idaho National Laboratory (INL) is tasked with the development of reactor physics analysis capability of the Next Generation Nuclear Power (NGNP) project. In order to examine INL's current prismatic reactor deterministic analysis tools, the project is conducting a benchmark exercise based on modeling the High Temperature Test Reactor (HTTR). This exercise entails the development of a model for the initial criticality, a 19 column thin annular core, and the fully loaded core critical condition with 30 columns. Special emphasis is devoted to the annular core modeling, which shares more characteristics with the NGNP base design. The DRAGON code is used in this study because it offers significant ease and versatility in modeling prismatic designs. Despite some geometric limitations, the code performs quite well compared to other lattice physics codes. DRAGON can generate transport solutions via collision probability (CP), method of characteristics (MOC), and discrete ordinates (Sn). A fine group cross section library based on the SHEM 281 energy structure is used in the DRAGON calculations. HEXPEDITE is the hexagonal z full core solver used in this study and is based on the Green's Function solution of the transverse integrated equations. In addition, two Monte Carlo (MC) based codes, MCNP5 and PSG2/SERPENT, provide benchmarking capability for the DRAGON and the nodal diffusion solver codes. The results from this study show a consistent bias of 2-3% for the core multiplication factor. This systematic error has also been observed in other HTTR benchmark efforts and is well documented in the literature. The ENDF/B VII graphite and U235 cross sections appear to be the main source of the error. The isothermal temperature coefficients calculated with the fully loaded core configuration agree well with other benchmark participants but are 40% higher than the experimental values. This discrepancy with the measurement stems from the fact that during the experiments the control rods were adjusted to maintain criticality, whereas in the model, the rod positions were fixed. In addition, this work includes a brief study of a cross section generation approach that seeks to decouple the domain in order to account for neighbor effects. This spectral interpenetration is a dominant effect in annular HTR physics. This analysis methodology should be further explored in order to reduce the error that is systematically propagated in the traditional generation of cross sections.
