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Fast Reactor Nuclear Technology

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Fast Reactor Nuclear Technology

Fast Reactor Nuclear Technology Book
Author : Joel Guidez
Publisher : Academic Press
Release : 2021-02-15
ISBN : 9780128219461
Language : En, Es, Fr & De

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Book Description :

Fast Reactor Nuclear Technology presents the current status of fast-reactor nuclear generation technology, with a focus on ecology and sustainability benefits for the future. Author Joel Guidez analyzes past failures and limited deployment reasons to help drive this power generation method forward to a cleaner and more sustainable energy environment. The book covers safety aspects, short-life waste management, multi-recycling and bio-diversity preservation to provide a well-rounded reference on the topic. Analyzes reasons for past failures and presents the advantages of fast reactor nuclear technology Reviews the status of fast reactor nuclear technology for sodium fast reactors and molten salt reactors with liquid fuel Presents ways in which fast nuclear reactors can help fight climate change and promote sustainability for the future

Experimental Breeder Reactor II EBR II

Experimental Breeder Reactor II  EBR II  Book
Author : Leonard J. Koch
Publisher : Amer Nuclear Society
Release : 2008
ISBN :
Language : En, Es, Fr & De

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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.

Fast Breeder Reactors

Fast Breeder Reactors Book
Author : P. V. Evans
Publisher : Elsevier
Release : 2016-06-06
ISBN : 148316134X
Language : En, Es, Fr & De

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Book Description :

Fast Breeder Reactors presents the proceedings of the London Conference on Fast Breeder Reactors organized by the British Nuclear Energy Society on May 17-19, 1966. The book covers topics about the place of the fast breeder reactor in the energy programs (including fuel cycles), operating experience with fast reactors; the design of fast reactor prototypes and power reactors (including advanced concepts with coolants other than sodium); fast reactor physics; and fuel technology. The text also describes topics about sodium technology and engineering of fast reactors and provides definitions of fast reactor breeding and inventory. Civil engineers will find the book useful.

Sodium Fast Reactors with Closed Fuel Cycle

Sodium Fast Reactors with Closed Fuel Cycle Book
Author : Baldev Raj,P. Chellapandi,P.R. Vasudeva Rao
Publisher : CRC Press
Release : 2015-04-15
ISBN : 1466587695
Language : En, Es, Fr & De

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Book Description :

Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book:Offers in-depth coverage of reactor physics, materials, design, s

Sustainable and Safe Nuclear Fission Energy

Sustainable and Safe Nuclear Fission Energy Book
Author : Günter Kessler
Publisher : Springer Science & Business Media
Release : 2012-05-08
ISBN : 3642119905
Language : En, Es, Fr & De

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Book Description :

Unlike existing books of nuclear reactor physics, nuclear engineering and nuclear chemical engineering this book covers a complete description and evaluation of nuclear fission power generation. It covers the whole nuclear fuel cycle, from the extraction of natural uranium from ore mines, uranium conversion and enrichment up to the fabrication of fuel elements for the cores of various types of fission reactors. This is followed by the description of the different fuel cycle options and the final storage in nuclear waste repositories. In addition the release of radioactivity under normal and possible accidental conditions is given for all parts of the nuclear fuel cycle and especially for the different fission reactor types.

Plentiful Energy

Plentiful Energy Book
Author : Charles E. Till,Yoon Il Chang
Publisher : CreateSpace
Release : 2011
ISBN : 9781466384606
Language : En, Es, Fr & De

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Book Description :

The Integral Fast Reactor (IFR) is a fast reactor system developed at Argonne National Laboratory in the decade 1984 to 1994. The IFR project developed the technology for a complete system; the reactor, the entire fuel cycle and the waste management technologies were all included in the development program. The reactor concept had important features and characteristics that were completely new and fuel cycle and waste management technologies that were entirely new developments. The reactor is a “fast” reactor – that is, the chain reaction is maintained by “fast” neutrons with high energy – which produces its own fuel. The IFR reactor and associated fuel cycle is a closed system. Electrical power is generated, new fissile fuel is produced to replace the fuel burned, its used fuel is processed for recycling by pyroprocessing – a new development – and waste is put in final form for disposal. All this is done on one self-sufficient site.The scale and duration of the project and its funding made it the largest nuclear energy R and D program of its day. Its purpose was the development of a long term massive new energy source, capable of meeting the nation's electrical energy needs in any amount, and for as long as it is needed, forever, if necessary. Safety, non-proliferation and waste toxicity properties were improved as well, these three the characteristics most commonly cited in opposition to nuclear power.Development proceeded from success to success. Most of the development had been done when the program was abruptly cancelled by the newly elected Clinton Administration. In his 1994 State of the Union address the president stated that “unnecessary programs in advanced reactor development will be terminated.” The IFR was that program.This book gives the real story of the IFR, written by the two nuclear scientists who were most deeply involved in its conception, the development of its R and D program, and its management.Between the scientific and engineering papers and reports, and books on the IFR, and the non-technical and often impassioned dialogue that continues to this day on fast reactor technology, we felt there is room for a volume that, while accurate technically, is written in a manner accessible to the non-specialist and even to the non-technical reader who simply wants to know what this technology is.

Fast Reactor Safety

Fast Reactor Safety Book
Author : John Graham
Publisher : Elsevier
Release : 2012-12-02
ISBN : 0323152651
Language : En, Es, Fr & De

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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.

Fast Spectrum Reactors

Fast Spectrum Reactors Book
Author : Alan E. Waltar,Donald R. Todd,Pavel V. Tsvetkov
Publisher : Springer Science & Business Media
Release : 2011-09-28
ISBN : 9781441995728
Language : En, Es, Fr & De

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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).

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 Book
Author : Willem Frederik Geert van Rooijen
Publisher : IOS Press
Release : 2006
ISBN : 9781586036966
Language : En, Es, Fr & De

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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. "

Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes

Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes Book
Author : M. Saito,T. Sawada
Publisher : Elsevier
Release : 2002-11-25
ISBN : 9780080441733
Language : En, Es, Fr & De

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Book Description :

This volume is a collection of the papers presented at the International Seminar on Advanced Nuclear Energy Systems toward Zero Release of Radioactive Wastes, which was held in Japan in November 2000. Scientists and engineers working in academia, research organizations and industry came together to discuss the role and contributions of nuclear energy to the environmental issues in the new millennium. It provided a forum for open discussions about the pursuit of solutions for the reduction of nuclear wastes based on the accelerator and fusion technologies, in addition to the advanced fission technology to harmonize the nuclear energy systems with the global environment. It also promoted future international collaboration in the following research fields: the role of nuclear energy in the new millennium; waste management; transmutation of minor actinides and fission products; advanced fission systems, accelerator driven systems, fusion systems, nuclear database, and advanced nuclear fuel cycles for transmutation of wastes. Published originally as a special issue (volume 40/3-4) of the international journal Progress in Nuclear Energy.

Nuclear Energy Materials And Reactors Volume II

Nuclear Energy Materials And Reactors   Volume II Book
Author : Yassin A. Hassan,Robin A. Chaplin
Publisher : EOLSS Publications
Release : 2010-09-22
ISBN : 1848263120
Language : En, Es, Fr & De

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Book Description :

Nuclear Energy Materials and Reactors is a component of Encyclopedia of Energy Sciences, Engineering and Technology Resources in the global Encyclopedia of Life Support Systems (EOLSS), which is an integrated compendium of twenty one Encyclopedias. Nuclear energy is a type of technology involving the controlled use of nuclear fission to release energy for work including propulsion, heat, and the generation of electricity. The theme on Nuclear Energy Materials and Reactors discusses: Fundamentals of Nuclear Energy; Nuclear Physics; Nuclear Interactions; Nuclear Reactor Theory; Nuclear Reactor Design; Nuclear Reactor Kinetics; Reactivity Changes; Nuclear Power Plants; Pressurized Water Reactors; Boiling Water Reactors; Pressurized Heavy Water Reactors; Heavy Water Light Water Reactors; Advanced Gas Cooled Reactors; Light Water Graphite Reactors; High Temperature Gas Cooled Reactors; Pebble Bed Modular Reactor; Radioactive Wastes, Origins, Classification and Management; Nuclear Reactor Overview and Reactor Cycles; The Nuclear Reactor Closed Cycle; Safety of Boiling Water Reactors; Supercritical Water-Cooled Nuclear Reactors: Review and Status; The Gas-Turbine Modular Helium Reactor; Application of Risk Assessment to Nuclear Power Plants; Production and Recycling Resources for Nuclear Fission. These two volumes are aimed at the following five major target audiences: University and College students Educators, Professional practitioners, Research personnel and Policy analysts, managers, and decision makers.

Super Light Water Reactors and Super Fast Reactors

Super Light Water Reactors and Super Fast Reactors Book
Author : Yoshiaki Oka,Seiichi Koshizuka,Yuki Ishiwatari,Akifumi Yamaji
Publisher : Springer Science & Business Media
Release : 2010-07-01
ISBN : 1441960341
Language : En, Es, Fr & De

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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 Neutron Kinetics of Nuclear Power Reactors

An Introduction to the Neutron Kinetics of Nuclear Power Reactors Book
Author : J. G. Tyror,R. I. Vaughan
Publisher : Elsevier
Release : 2013-10-22
ISBN : 1483148920
Language : En, Es, Fr & De

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Book Description :

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.

Handbook of Small Modular Nuclear Reactors

Handbook of Small Modular Nuclear Reactors Book
Author : Mario D Carelli,Daniel T Ingersoll
Publisher : Elsevier
Release : 2014-09-22
ISBN : 0857098535
Language : En, Es, Fr & De

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Book Description :

Small modular reactors (SMRs) are an advanced, safe type of nuclear reactor technology that are suitable for small and medium sized applications including both power and heat generation. In particular, their use as individual units or in combination to scale-up capacity offer benefits in terms of siting, installation, operation, lifecycle and economics in comparison to the development of larger nuclear plant for centralised electricity power grids. Interest has increased in the research and development of SMRs for both developing countries as well as such additional cogeneration options as industrial/chemical process heat, desalination and district heating, and hydrogen production. This book reviews key issues in their development as well as international R&D in the field. Gives an overview of small modular reactor technology Reviews the design characteristics of integral pressurized water reactors and focuses on reactor core and fuel technologies, key reactor system components, instrumentation and control, human-system interfaces and safety Considers the economics, financing, licensing, construction methods and hybrid energy systems of small modular reactors Describes SMR development activities worldwide, and concludes with a discussion of how SMR deployment can contribute to the growth of developing countries

Heat Pipe Applications in Fission Driven Nuclear Power Plants

Heat Pipe Applications in Fission Driven Nuclear Power Plants Book
Author : Bahman Zohuri
Publisher : Springer
Release : 2019-02-14
ISBN : 3030058824
Language : En, Es, Fr & De

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Book Description :

This book presents a new and innovative approach for the use of heat pipes and their application in a number of industrial scenarios, including space and nuclear power plants. The book opens by describing the heat pipe and its concept, including sizing, composition and binding energies. It contains mathematical models of high and low temperature pipes along with extensive design and manufacturing models, characteristics and testing programs. A detailed design and safety analysis concludes the book, emphasizing the importance of heat pipe implementation within the main cooling system and within the core of the reactor, making this book a useful resource for students, engineers, and researchers.

Future of the Nuclear Security Environment in 2015

Future of the Nuclear Security Environment in 2015 Book
Author : Russian Academy of Sciences,National Academy of Sciences,Policy and Global Affairs,Committee on International Security and Arms Control,Joint Committees on the Future of the Nuclear Security Environment in 2015
Publisher : National Academies Press
Release : 2009-02-02
ISBN : 9780309177320
Language : En, Es, Fr & De

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Book Description :

The U.S. National Academies (NAS) and the Russian Academy of Sciences (RAS), building on a foundation of years of interacademy cooperation, conducted a joint project to identify U.S. and Russian views on what the international nuclear security environment will be in 2015, what challenges may arise from that environment, and what options the U.S. and Russia have in partnering to address those challenges. The project's discussions were developed and expanded upon during a two-day public workshop held at the International Atomic Energy Agency in November 2007. A key aspect of that partnership may be cooperation in third countries where both the U.S. and Russia can draw on their experiences over the last decade of non-proliferation cooperation. More broadly, the following issues analyzed over the course of this RAS-NAS project included: safety and security culture, materials protection, control and accounting (MPC&A) best practices, sustainability, nuclear forensics, public-private partnerships, and the expansion of nuclear energy.