Author: B. R. HaywardPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 40
Book Description
Radiation Behavior of Metallic Fuels for Sodium Graphite Reactors
Author: B. R. HaywardPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 40
Book Description
Transient Behavior of an Advanced Sodium Graphite Reactor
Author: H. H. CappelPublisher:
ISBN:
Category : Nuclear reactor kinetics
Languages : en
Pages : 60
Book Description
Properties of Ceramic and Cermet Fuels for Sodium Graphite Reactors
Author: N. R. KoenigPublisher:
ISBN:
Category : Ceramic metals
Languages : en
Pages : 54
Book Description
The Effect of Nuclear Radiation on Metallic Fuel Materials
Author: A. A. BauėrPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 150
Book Description
Nuclear Fuel Elements
Author: Brian R. T. FrostPublisher: Elsevier
ISBN: 1483155250
Category : Technology & Engineering
Languages : en
Pages : 284
Book Description
Nuclear Fuel Elements: Design, Fabrication and Performance is concerned with the design, fabrication, and performance of nuclear fuel elements, with emphasis on fast reactor fuel elements. Topics range from fuel types and the irradiation behavior of fuels to cladding and duct materials, fuel element design and modeling, fuel element performance testing and qualification, and the performance of water reactor fuels. Fast reactor fuel elements, research and test reactor fuel elements, and unconventional fuel elements are also covered. This volume consists of 12 chapters and begins with an overview of nuclear reactors and fuel elements, as well as fuel element design and development based on the reactor operator's approach, materials scientist's approach, and interdisciplinary approach. The reader is then introduced to different types of nuclear fuels and their irradiation behavior, considerations for using cladding and duct materials in fuel element design and development, and fuel element design and modeling. The chapters that follow focus on the testing of fuel element performance, experimental techniques and equipment for testing fuel element designs, and the performance of fuels for water reactors. Fuel elements for gas-cooled reactors, fast reactors, and research and test reactors are also described. The book concludes with an assessment of unconventional fuel elements. This book will be useful to fuel element technologists as well as materials scientists and engineers.
Modelling of Thermo-mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors
Author: Aydin KarahanPublisher:
ISBN:
Category :
Languages : en
Pages : 344
Book Description
(Cont.) The FEAST-OXIDE predictions has been compared to the available FFTF, EBR-II and JOYO databases, and the agreement between the code and data was found to be satisfactory. Both metal and oxide versions of FEAST are rather superior compared to many other fuel codes in the literature. Comparing metal and oxide versions, FEAST-OXIDE has a more sophisticated fission gas release and swelling model, which is based on vacancy flow. In addition, modeling of the chemistry module of the oxide fuel requires a much more detailed analysis to estimate its impact on the thermo-mechanical behavior with a reasonable accuracy. Finally, the melting of the oxide fuel and its effect on the thermo-mechanical performance have been modeled in case of transient scenarios.
Radiation Damage in Graphite
Author: J. H. W. SimmonsPublisher: Elsevier
ISBN: 1483186490
Category : Technology & Engineering
Languages : en
Pages : 264
Book Description
Nuclear Energy, Volume 102: Radiation Damage in Graphite provides a general account of the effects of irradiation on graphite. This book presents valuable work on the structure of the defects produced in graphite crystals by irradiation. Organized into eight chapters, this volume begins with an overview of the description of the methods of manufacturing graphite and of its physical properties. This text then presents details of the method of setting up a scale of irradiation dose. Other chapters consider the effect of irradiation at a given temperature on a physical property of graphite. This book discusses as well the changes in dimensions produced by irradiation and the effects of irradiation on the mechanical properties of graphite. The final chapter deals with the accumulation of stored energy, which is one of the main problems caused by the irradiation of graphite in nuclear reactors. This book is a valuable resource for physicists and chemical physicists.
Report on Civilian Reactor Fuel Elements by the Civilian Reactor Fuel Element Review Group
Author: M. J. WhitmanPublisher:
ISBN:
Category : Fuel burnup (Nuclear engineering)
Languages : en
Pages : 204
Book Description
Comprehensive Nuclear Materials
Author: Todd R AllenPublisher: Elsevier
ISBN: 0080560334
Category : Technology & Engineering
Languages : en
Pages : 3552
Book Description
Comprehensive Nuclear Materials, Five Volume Set discusses the major classes of materials suitable for usage in nuclear fission, fusion reactors and high power accelerators, and for diverse functions in fuels, cladding, moderator and control materials, structural, functional, and waste materials. The work addresses the full panorama of contemporary international research in nuclear materials, from Actinides to Zirconium alloys, from the worlds' leading scientists and engineers. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environment Fully integrated with F-elements.net, a proprietary database containing useful cross-referenced property data on the lanthanides and actinides Details contemporary developments in numerical simulation, modelling, experimentation, and computational analysis, for effective implementation in labs and plants
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Author: D. G. HarringtonPublisher:
ISBN:
Category : Uranium
Languages : en
Pages : 40
Book Description