Innovative Design of Uranium Startup Fast Reactors PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download Innovative Design of Uranium Startup Fast Reactors PDF full book. Access full book title Innovative Design of Uranium Startup Fast Reactors by Tingzhou Fei. Download full books in PDF and EPUB format.
Author: Tingzhou Fei Publisher: ISBN: Category : Languages : en Pages : 283
Book Description
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, deployment of fast reactors requires decoupling from reprocessing facilities. This motivates the design and deployment of Uranium Startup sodium Fast Reactors (USFR) on a once-through fuel cycle in order to facilitate the transition to fast reactors by reducing their plant costs and increase capacity factor. Three different fuel types including uranium carbide (UC), metal (UZr) and uranium oxide (UO2) are investigated and analyzed using the ERANOS code for potential use in USFR designs. A key enabling factor is use of high-albedo MgO or Zr reflectors in place of fertile blankets to reduce uranium enrichment and improve non-proliferation resistance. The different compositions in different fuel types result in different neutronic performance. The softer spectrum and lower allowable fuel volume fractions of oxide fuel have shorter fuel cycle length due to reactivity constraints, whereas fast neutron fluence plays an important role in determining the fuel cycle length in metal cores due to the harder spectrum. Moderators are deliberately added in the metal fuels to lower the fast neutron fluence. Carbide cores have a slightly harder neutron spectrum than oxide cores and a larger achievable fuel volume fraction. USFRs using all three fuel types (UC, U0 2 and UZr) have lower fuel cycle cost (6.27, 6.09 and 5.77mills/kWhe) and comparable uranium consumption (0.50, 0.55, and 0.53kgNatU/MWde) compared with typical LWRs (6.39nills/kWhe and 0.53kgNatU/MWde). All USFR designs have maximum neutron fluence below 5E23n/cm2. All three USFR designs have pressure drop below 0.7MPa and maximum temperature below the limit for each fuel type. Both carbide and metal fuel have excellent passive safety performance. It is concluded that the USFR approach is a competitive way to accelerate fast reactor development.
Author: Tingzhou Fei Publisher: ISBN: Category : Languages : en Pages : 283
Book Description
Sodium Fast Reactors are one of the three candidates of GEN-IV fast reactors. Fast reactors play an important role in saving uranium resources and reducing nuclear wastes. Conventional fast reactors rely on transuranic fuels from reprocessing facilities, which are not available in the U.S. Thus, deployment of fast reactors requires decoupling from reprocessing facilities. This motivates the design and deployment of Uranium Startup sodium Fast Reactors (USFR) on a once-through fuel cycle in order to facilitate the transition to fast reactors by reducing their plant costs and increase capacity factor. Three different fuel types including uranium carbide (UC), metal (UZr) and uranium oxide (UO2) are investigated and analyzed using the ERANOS code for potential use in USFR designs. A key enabling factor is use of high-albedo MgO or Zr reflectors in place of fertile blankets to reduce uranium enrichment and improve non-proliferation resistance. The different compositions in different fuel types result in different neutronic performance. The softer spectrum and lower allowable fuel volume fractions of oxide fuel have shorter fuel cycle length due to reactivity constraints, whereas fast neutron fluence plays an important role in determining the fuel cycle length in metal cores due to the harder spectrum. Moderators are deliberately added in the metal fuels to lower the fast neutron fluence. Carbide cores have a slightly harder neutron spectrum than oxide cores and a larger achievable fuel volume fraction. USFRs using all three fuel types (UC, U0 2 and UZr) have lower fuel cycle cost (6.27, 6.09 and 5.77mills/kWhe) and comparable uranium consumption (0.50, 0.55, and 0.53kgNatU/MWde) compared with typical LWRs (6.39nills/kWhe and 0.53kgNatU/MWde). All USFR designs have maximum neutron fluence below 5E23n/cm2. All three USFR designs have pressure drop below 0.7MPa and maximum temperature below the limit for each fuel type. Both carbide and metal fuel have excellent passive safety performance. It is concluded that the USFR approach is a competitive way to accelerate fast reactor development.
Author: Naoto Kasahara Publisher: Springer ISBN: 9811028214 Category : Technology & Engineering Languages : en Pages : 307
Book Description
This book describes the fast reactor (FR), a type of new reactor for nuclear plants, currently under research and development. The book targets young researchers and engineers who will be charged with commercializing this new type of reactor to lead to the development of new components and systems for improved plant reliability and economy. This volume also helps readers to understand the methods of integrating the power plant in its entirety, from the reactor core to all of the various systems and components, and teaches the way of thinking that forms the background of these methods. This background includes the various organizational and management issues that are encountered as projects move forward and will be explored in great detail based on actual design and construction experience with Japan’s prototype FR, Monju.
Author: Rebecca Elizabeth Krentz-Wee Publisher: ISBN: Category : Languages : en Pages : 28
Book Description
In order to improve a new design for a uranium startup sodium cooled fast reactor which was proposed at MIT, this thesis evaluated radial power flattening by varying the fuel volume fraction at a fixed U-235 enrichment of 18.5%. Of particular interest was how best to reduce the radial power peaking at the center of the reactor. Two cores were modeled: one with a uniform fuel volume fraction of 37% and one with fuel volume fractions which increased with the core radius. The ERANOS code was used to determine the power density, reactivity, and material values at the beginning and end of life. The varied fuel was shown to have a flatter radial power profile, but slightly lower reactivity and more mass. The power in each cell was normalized with respect to the average power; the peak power ratio in the uniform fuel volume core was 1.59, while the peak power ratio in the varied fuel volume core was 1.16, a significant improvement. The reactivity at beginning of life dropped from 12573.9 pcm to 11734.0 pcm, and stayed about 500pcm lower over the cycle, which is not a very large amount. The total mass of the heavy metals increased from the uniform core to the varied core by less than 0.9% and the mass of U-235 by 1.2%, so the varied fuel does not significantly impact the overall fuel cycle cost.
Author: International Atomic Energy Agency Publisher: ISBN: 9781523130191 Category : Fast reactors Languages : en Pages : 0
Book Description
"Based on a recommendation from the Technical Working Group on Fast Reactors, this publication is a regular update of previous publications on fast reactor technology. The publication provides comprehensive and detailed information on the technology of fast neutron reactors. The focus is on practical issues that are useful to engineers, scientists, managers, university students and professors. The main issues of discussion are experience in design, construction, operation and decommissioning, various areas of research and development, engineering, safety and national strategies, and public acceptance of fast reactors. In the summary the reader will find national strategies, international initiatives on innovative (i.e. Generation IV) systems and an assessment of public acceptance as related to fast reactors."--Résumé de l'éditeur.
Author: Bahman Zohuri Publisher: Springer ISBN: 3319705512 Category : Technology & Engineering Languages : en Pages : 407
Book Description
The second edition of this book includes the most up-to-date details on the advantages of Nuclear Air-Brayton Power Plant Cycles for advanced reactors. It demonstrates significant advantages for typical sodium cooled reactors and describes how these advantages will grow as higher temperature systems (molten salts) are developed. It also describes how a Nuclear Air-Brayton system can be integrated with significant renewable (solar and wind) energy systems to build a low carbon grid. Starting with basic principles of thermodynamics as applied to power plant systems, it moves on to describe several types of Nuclear Air-Brayton systems that can be employed to meet different requirements. It provides estimates of component sizes and performance criteria for Small Modular Reactors (SMR). This book has been revised to include updated tables and significant new results that have become available for intercooled systems in the time since the previous edition published. In this edition also, the steam tables have been updated and Chapters 9 and 10 have been rewritten to keep up with the most up-to- date technology and current research.
Author: Allan S. Krass Publisher: Routledge ISBN: 100020054X Category : Political Science Languages : en Pages : 325
Book Description
Originally published in 1983, this book presents both the technical and political information necessary to evaluate the emerging threat to world security posed by recent advances in uranium enrichment technology. Uranium enrichment has played a relatively quiet but important role in the history of efforts by a number of nations to acquire nuclear weapons and by a number of others to prevent the proliferation of nuclear weapons. For many years the uranium enrichment industry was dominated by a single method, gaseous diffusion, which was technically complex, extremely capital-intensive, and highly inefficient in its use of energy. As long as this remained true, only the richest and most technically advanced nations could afford to pursue the enrichment route to weapon acquisition. But during the 1970s this situation changed dramatically. Several new and far more accessible enrichment techniques were developed, stimulated largely by the anticipation of a rapidly growing demand for enrichment services by the world-wide nuclear power industry. This proliferation of new techniques, coupled with the subsequent contraction of the commercial market for enriched uranium, has created a situation in which uranium enrichment technology might well become the most important contributor to further nuclear weapon proliferation. Some of the issues addressed in this book are: A technical analysis of the most important enrichment techniques in a form that is relevant to analysis of proliferation risks; A detailed projection of the world demand for uranium enrichment services; A summary and critique of present institutional non-proliferation arrangements in the world enrichment industry, and An identification of the states most likely to pursue the enrichment route to acquisition of nuclear weapons.
Author: Thomas James Dolan Publisher: Elsevier ISBN: 0323993567 Category : Technology & Engineering Languages : en Pages : 1068
Book Description
Molten Salt Reactors and Thorium Energy, Second Edition is a fully updated comprehensive reference on the latest advances in MSR research and technology. Building on the successful first edition, Tom Dolan and the team of experts have fully updated the content to reflect the impressive advances from the last 5 years, ensuring this book continues to be the go-to reference on the topic. This new edition covers progress made in MSR design, details innovative experiments, and includes molten salt data, corrosion studies and deployment plans. The successful case studies section of the first edition have been removed, expanded, and fully updated, and are now published in a companion title called Global Case Studies on Molten Salt Reactors. Readers will gain a deep understanding of the advantages and challenges of MSR development and thorium fuel use, as well as step-by-step guidance on the latest in MSR reactor design. Each chapter provides a clear introduction, covers technical issues and includes examples and conclusions, while promoting the sustainability benefits throughout. A fully updated comprehensive handbook on Molten Salt Reactors and Thorium Energy, written by a team of global experts Covers MSR applications, technical issues, reactor types and reactor designs Includes 3 brand new chapters which reflect the latest advances in research and technology since the first edition published Presents case studies on molten salt reactors which aid in the transition to net zero by providing abundant clean, safe energy to complement wind and solar powe
Author: Staffan Alexander Qvist Publisher: ISBN: Category : Languages : en Pages : 650
Book Description
In light of the scientific evidence for changes in the climate caused by greenhouse-gas emissions from human activities, the world is in ever more desperate need of new, inexhaustible, safe and clean primary energy sources. A viable solution to this problem is the widespread adoption of nuclear breeder reactor technology. Innovative breeder reactor concepts using liquid-metal coolants such as sodium or lead will be able to utilize the waste produced by the current light water reactor fuel cycle to power the entire world for several centuries to come. Breed & burn (B & B) type fast reactor cores can unlock the energy potential of readily available fertile material such as depleted uranium without the need for chemical reprocessing. Using B & B technology, nuclear waste generation, uranium mining needs and proliferation concerns can be greatly reduced, and after a transitional period, enrichment facilities may no longer be needed. In this dissertation, new passively operating safety systems for fast reactors cores are presented. New analysis and optimization methods for B & B core design have been developed, along with a comprehensive computer code that couples neutronics, thermal-hydraulics and structural mechanics and enables a completely automated and optimized fast reactor core design process. In addition, an experiment that expands the knowledge-base of corrosion issues of lead-based coolants in nuclear reactors was designed and built. The motivation behind the work presented in this thesis is to help facilitate the widespread adoption of safe and efficient fast reactor technology.
Author: International Atomic Energy Agency Publisher: ISBN: 9789201364104 Category : Science Languages : en Pages : 0
Book Description
As a part of the IAEA efforts for knowledge preservation and data retrieval, this publication compiles and documents significant aspects of fast reactor engineering development and experience. Its focus is on research and development activities, experience with experimental facilities, and criteria for comparison liquid metal coolants.
Author: Tingzhou Fei
Author: Tingzhou Fei
Author: Naoto Kasahara
Author: Rebecca Elizabeth Krentz-Wee
Author: U.S. Atomic Energy Commission. Division of Reactor Development
Author: International Atomic Energy Agency
Author: Bahman Zohuri
Author: Allan S. Krass
Author: Thomas James Dolan
Author: Staffan Alexander Qvist
Author: International Atomic Energy Agency