Fast Reactor System Design

Fast Reactor System Design PDF Author: Naoto Kasahara
Publisher: Springer
ISBN: 9811028214
Category : Technology & Engineering
Languages : en
Pages : 307

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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.

Fast Reactor System Design

Fast Reactor System Design PDF Author: Naoto Kasahara
Publisher: Springer
ISBN: 9811028214
Category : Technology & Engineering
Languages : en
Pages : 307

Get Book Here

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.

Fast Reactor Safety

Fast Reactor Safety PDF Author: John Graham
Publisher: Elsevier
ISBN: 0323152651
Category : Technology & Engineering
Languages : en
Pages : 390

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Book Description
Fast Reactor Safety deals with safety design criteria and methodology for fast reactors. Topics covered include safety evaluation methods, system disturbances, containment, and licensing. The characteristics of fast reactors, including heat ratings and coolants, are also discussed. Comprised of six chapters, this book opens with an overview of methods used to evaluate nuclear safety, along with neutron kinetics, thermal and feedback effects, and fault tree analysis. The reader is then introduced to possible system disturbances in relation to three distinct fast reactor systems: liquid-metal-cooled fast breeder reactors, gas-cooled fast breeder reactors, and steam-cooled fast breeder reactors. The next chapter looks at safety criteria that are set to define the design of a safe plant, together with the safety features that might be included. The remaining chapters focus on the particular problems of a sodium-cooled design; containment building and primary circuit and vessel containment; and licensing of the plant. This monograph is intended for graduates and undergraduates in nuclear engineering who are attending courses in reactor safety.

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor

Improving Fuel Cycle Design and Safety Characteristics of a Gas Cooled Fast Reactor PDF Author: Willem Frederik Geert van Rooijen
Publisher: IOS Press
ISBN: 9781586036966
Category : Technology & Engineering
Languages : en
Pages : 160

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Book Description
The Generation IV Forum is an international nuclear energy research initiative aimed at developing the fourth generation of nuclear reactors, envisaged to enter service halfway the 21st century. One of the Generation IV reactor systems is the Gas Cooled Fast Reactor (GCFR), the subject of study in this thesis. The Generation IV reactor concepts should improve all aspects of nuclear power generation. Within Generation IV, the GCFR concept specifically targets sustainability of nuclear power generation. The Gas Cooled Fast Reactor core power density is high in comparison to other gas cooled reactor concepts. Like all nuclear reactors, the GCFR produces decay heat after shut down, which has to be transported out of the reactor under all circumstances. The layout of the primary system therefore focuses on using natural convection Decay Heat Removal (DHR) where possible, with a large coolant fraction in the core to reduce friction losses.

Fast Spectrum Reactors

Fast Spectrum Reactors PDF Author: Alan E. Waltar
Publisher: Springer Science & Business Media
ISBN: 1441995722
Category : Technology & Engineering
Languages : en
Pages : 717

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Book Description
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).

Super Light Water Reactors and Super Fast Reactors

Super Light Water Reactors and Super Fast Reactors PDF Author: Yoshiaki Oka
Publisher: Springer Science & Business Media
ISBN: 1441960341
Category : Technology & Engineering
Languages : en
Pages : 664

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Book Description
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.

An Introduction to the Engineering of Fast Nuclear Reactors

An Introduction to the Engineering of Fast Nuclear Reactors PDF Author: Anthony M. Judd
Publisher: Cambridge University Press
ISBN: 1107782953
Category : Science
Languages : en
Pages : 303

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Book Description
An invaluable resource for both graduate-level engineering students and practising nuclear engineers who want to expand their knowledge of fast nuclear reactors, the reactors of the future. This book is a concise yet comprehensive introduction to all aspects of fast reactor engineering. It covers topics including neutron physics; neutron flux spectra; flux distribution; Doppler and coolant temperature coefficients; the performance of ceramic and metal fuels under irradiation, structural changes, and fission-product migration; the effects of irradiation and corrosion on structural materials, irradiation swelling; heat transfer in the reactor core and its effect on core design; coolants including sodium and lead-bismuth alloy; coolant circuits; pumps; heat exchangers and steam generators; and plant control. The book includes new discussions on lead-alloy and gas coolants, metal fuel, the use of reactors to consume radioactive waste, and accelerator-driven subcritical systems.

A Description of Integral Physics Data for Fast Reactor Design

A Description of Integral Physics Data for Fast Reactor Design PDF Author: W. B. Loewenstein
Publisher:
ISBN:
Category : Criticality (Nuclear engineering)
Languages : en
Pages : 36

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Book Description
Integral physics data for fast reactor design are discussed. The measurements needed include those of critical mass, shape factor, detector ratios, neutron spectra, material replacement experiments, reflector savings, neutron lifetime, Rossi- alpha, and similar quantities. Topics covered include plutonium and uranium-233-fueled systems, highly enriched uranium-235 systems in optimum geometry, uranium cores of various enrichments and dilutions, extreme geometry critical experiments, specific reactor systems, core mockup in-homogeneities, spectral studies and detector ratios, uranium equilibrium spectrum data, material replacement measurements, fast reactor dynamics, and suggested future experiments and experimental programs.

Nuclear Reactor Design

Nuclear Reactor Design PDF Author: Yoshiaki Oka
Publisher: Springer
ISBN: 443154898X
Category : Technology & Engineering
Languages : en
Pages : 337

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Book Description
This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Initial Requirements for Gas-Cooled Fast Reactor (GFR) System Design, Performance, and Safety Analysis Models

Initial Requirements for Gas-Cooled Fast Reactor (GFR) System Design, Performance, and Safety Analysis Models PDF Author: Kevan D. Weaver
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Book Description
The gas-cooled fast reactor (GFR) was chosen as one of the Generation IV nuclear reactor systems to be developed based on its excellent potential for sustainability through reduction of the volume and radio toxicity of both its own fuel and other spent nuclear fuel, and for extending/utilizing uranium resources orders of magnitude beyond what the current open fuel cycle can realize. In addition, energy conversion at high thermal efficiency is possible with the current designs being considered, thus increasing the economic benefit of the GFR. However, research and development challenges include the ability to use passive decay heat removal systems during accident conditions, survivability of fuels and in-core materials under extremetemperatures and radiation, and economical and efficient fuel cycle processes. Nevertheless, the GFR was chosen as one of only six Generation IV systems to be pursued based on its ability tomeet the Generation IV goals in sustainability, economics, safety and reliability, proliferation resistance and physical protection.

Experimental Breeder Reactor-II (EBR-II)

Experimental Breeder Reactor-II (EBR-II) PDF Author: Leonard J. Koch
Publisher:
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 264

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Book Description
Koch, former manager of the Experimental Breeder Reactor-II (EBR-II), offers a first-hand account of the development, design, construction, and initial operation of this facility, which has contributed to the foundation of knowledge for all fast reactors. He explains why certain design choices were made while others were rejected. He also outlines how he thinks that future sodium cooled fast reactors should be designed, based on the experience gained with EBR-II. An appendix traces the lineage of EBR-II, including original memos and meeting notes, beginning with Enrico Fermi and Walter Zinn and progressing to the formation of the EBR-II project. B&w photos and illustrations are included. The book is of interest to designers of future fast reactors. There is no subject index.