Accident Tolerant Materials for Light Water Reactor Fuels

Accident Tolerant Materials for Light Water Reactor Fuels
Author: Raul B. Rebak
Publsiher: Unknown
Total Pages: 236
Release: 2020-01-06
ISBN 10: 0128175036
ISBN 13: 9780128175033
Language: EN, FR, DE, ES & NL

Accident Tolerant Materials for Light Water Reactor Fuels Book Review:

Accident Tolerant Materials for Light Water Reactor Fuels provides a description of what an accident tolerant fuel is and the benefits and detriments of each concept. The book begins with an introduction to nuclear power as a renewable energy source and the current materials being utilized in light water reactors. It then moves on to discuss the recent advancements being made in accident tolerant fuels, reviewing the specific materials, their fabrication and implementation, environmental resistance, irradiation behavior, and licensing requirements. The book concludes with a look to the future of new power generation technologies. It is written for scientists and engineers working in the nuclear power industry and is the first comprehensive work on this topic. Introduces the fundamental description of accident tolerant fuel, including fabrication and implementation Describes both the benefits and detriments of the various Accident Tolerant Fuel concepts Includes information on the process of materials selection with a discussion of how and why specific materials were chosen, as well as why others failed

Energy and Water Development Appropriations for 2013 Department of Energy DOE DOE Nuclear energy and Nuclear Regulatory Commission FY 2013 budget

Energy and Water Development Appropriations for 2013  Department of Energy  DOE  DOE Nuclear energy and Nuclear Regulatory Commission FY 2013 budget
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 329
Release: 2013
ISBN 10:
ISBN 13: MINN:31951D03670360P
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2013 Department of Energy DOE DOE Nuclear energy and Nuclear Regulatory Commission FY 2013 budget Book Review:

Energy and Water Development Appropriations for 2014 Department of Energy fiscal year 2014 justifications

Energy and Water Development Appropriations for 2014  Department of Energy fiscal year 2014 justifications
Author: United States. Congress. House. Committee on Appropriations. Subcommittee on Energy and Water Development
Publsiher: Unknown
Total Pages: 329
Release: 2013
ISBN 10:
ISBN 13: UCR:31210023707662
Language: EN, FR, DE, ES & NL

Energy and Water Development Appropriations for 2014 Department of Energy fiscal year 2014 justifications Book Review:

Advances in Nuclear Fuel Chemistry

Advances in Nuclear Fuel Chemistry
Author: Markus H.A. Piro
Publsiher: Woodhead Publishing
Total Pages: 670
Release: 2020-03-20
ISBN 10: 008102651X
ISBN 13: 9780081026519
Language: EN, FR, DE, ES & NL

Advances in Nuclear Fuel Chemistry Book Review:

Advances in Nuclear Fuel Chemistry presents a high-level description of nuclear fuel chemistry based on the most recent research and advances. Dr. Markus H.A. Piro and his team of global, expert contributors cover all aspects of both the conventional uranium-based nuclear fuel cycle and non-conventional fuel cycles, including mining, refining, fabrication, and long-term storage, as well as emerging nuclear technologies, such as accident tolerant fuels and molten salt materials. Aimed at graduate students, researchers, academics and practicing engineers and regulators, this book will provide the reader with a single reference from which to learn the fundamentals of classical thermodynamics and radiochemistry. Consolidates the latest research on nuclear fuel chemistry into one comprehensive reference, covering all aspects of traditional and non-traditional nuclear fuel cycles Includes contributions from world-renowned experts from many countries representing government, industry and academia Covers a variety of fuel designs, including conventional uranium dioxide, mixed oxides, research reactor fuels, and molten salt fuels Written by experts with hands-on experience in the development of such designs

Nuclear Science Abstracts

Nuclear Science Abstracts
Author: Anonim
Publsiher: Unknown
Total Pages: 329
Release: 1967
ISBN 10:
ISBN 13: UOM:39015023544441
Language: EN, FR, DE, ES & NL

Nuclear Science Abstracts Book Review:

Nuclear Materials Science

Nuclear Materials Science
Author: Karl R. Whittle
Publsiher: Iop Publishing Limited
Total Pages: 100
Release: 2016-03-21
ISBN 10: 9780750311052
ISBN 13: 0750311053
Language: EN, FR, DE, ES & NL

Nuclear Materials Science Book Review:

Concerns around global warming have led to a nuclear renaissance in many countries. Meanwhile, the nuclear industry is already warning of a need to train more nuclear engineers and scientists who are needed in a range of areas from healthcare and radiation detection to space exploration and advanced materials, as well as for the nuclear power industry. Here, Karl Whittle provides a solid overview of the intersection of nuclear engineering and materials science at a level approachable by advanced students from materials, engineering and physics. The text explains the unique aspects needed in the design and implementation of materials for use in demanding nuclear settings. In addition to material properties and their interaction with radiation, the book covers a range of topics including reactor design, fuels, fusion, future technologies and lessons learned from past incidents. Accompanied by problems, videos and teaching aids, the book is suitable for a course text in nuclear materials and a reference for those already working in the field.

Thermal Hydraulics of Accident Tolerant Fuel Concepts and a Preliminary Demonstration of CASL s Coupled Tools for BWRs

Thermal Hydraulics of Accident Tolerant Fuel Concepts and a Preliminary Demonstration of CASL s Coupled Tools for BWRs
Author: Jacob Preston Gorton
Publsiher: Unknown
Total Pages: 329
Release: 2018
ISBN 10:
ISBN 13: OCLC:1083898035
Language: EN, FR, DE, ES & NL

Thermal Hydraulics of Accident Tolerant Fuel Concepts and a Preliminary Demonstration of CASL s Coupled Tools for BWRs Book Review:

Since the 2011 accident at the Daiichi nuclear power plant in Fukushima, Japan, there has been a worldwide effort to develop so-called accident tolerant fuel (ATF) technologies to enhance safety during design basis and beyond design basis accidents. Part of the ATF development effort involves replacing much of the zirconium-based materials in light water reactors (LWRs). This is due to the accelerated oxidation rate of zirconium at high temperatures potentially experienced during severe accidents, which led to the build-up of hydrogen gas and eventual explosions that occurred at the Daiichi nuclear power plant. To be considered as a possible alternative to zirconium, an ATF candidate material must not only have greater oxidation resistance but must also have equal or better performance than zirconium in reactor operations and safety. Two candidate materials that may meet these requirements are iron-chromium-aluminum (FeCrAl) alloys and silicon carbide fiber-reinforced, silicon carbide matrix composites (SiC/SiC). Two studies on ATF concepts are presented in this thesis, which focus on using computer simulations to evaluate the use of FeCrAl as the fuel rod cladding material in a pressurized water reactor (PWR) and the use of SiC/SiC as the fuel assembly channel box material in a boiling water reactor (BWR). Both of these studies are performed using computer modeling, which is one of the first steps for evaluating new design concepts and eventually integrating them into existing reactors. Developing tools that can accurately predict the performance of nuclear reactors with high fidelity is the goal of the Consortium for Advanced Simulation of Light Water Reactors (CASL). Also included in this thesis is a preliminary demonstration of neutronic-to-thermal-hydraulic coupled BWR simulations performed using the CASL tools MPACT and CTF. In the first study, a model of a PWR fuel assembly was created to predict the critical heat flux (CHF) of FeCrAl fuel rod cladding during an imposed 50% overpower condition, which may be representative of an accident condition. CHF is a critical parameter to evaluate for ATF candidate materials because reaching CHF in a fuel rod can cause a rapid increase in temperature in the reactor that may lead to bursting of the cladding and a loss of ability to cool the core. Current correlations used for predicting flow boiling CHF in reactors are not dependent on material or surface characteristics, but this study showed that preliminary pool boiling results could be used to modify existing CHF correlations to make them more applicable to a given material, such as FeCrAl. Preliminary transient flow boiling experiments are also analyzed in this thesis for Inconel 600 and Stainless Steel 316, which pave the way for future flow boiling experiments using FeCrAl. In the second study, BWR fuel assembly models were created with a SiC/SiC channel box to predict a spatial temperature and fast neutron flux distribution in the channel box. The temperature and fast flux distributions were then used as boundary conditions for a finite element model of the channel box created by Oak Ridge National Laboratory to determine the deflection of the channel box due to temperature and neutron flux gradients. It was found in this study that the deflection of the channel box, which was mainly a product of the nonuniform fast flux distribution causing a swelling gradient within the channel box, may lead to interference with control blades in BWR cores. The work presented in this thesis provides new information on two ATF concepts and helps lay the groundwork for future evaluations. Detailed computational evaluations are an important step in the progression and application of these concepts that have the potential to increase the safety of nuclear reactors. The development of high-fidelity computational tools like MPACT/CTF is important for providing accurate simulated results that can be used in advancing the development of ATF concepts.

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems     Water Reactors
Author: John H. Jackson,Denise Paraventi,Michael Wright
Publsiher: Springer
Total Pages: 2532
Release: 2018-12-20
ISBN 10: 3030046397
ISBN 13: 9783030046392
Language: EN, FR, DE, ES & NL

Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors Book Review:

This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.

Light Water Reactor Materials

Light Water Reactor Materials
Author: Arthur T. Motta,Donald R. Olander,Brian Wirth
Publsiher: Unknown
Total Pages: 329
Release: 2017
ISBN 10: 9780894484612
ISBN 13: 0894484613
Language: EN, FR, DE, ES & NL

Light Water Reactor Materials Book Review:

Volume 1. Fundamentals

Nuclear Engineering Handbook Second Edition

Nuclear Engineering Handbook  Second Edition
Author: Kenneth D. Kok
Publsiher: CRC Press
Total Pages: 978
Release: 2016-10-03
ISBN 10: 1315356309
ISBN 13: 9781315356303
Language: EN, FR, DE, ES & NL

Nuclear Engineering Handbook Second Edition Book Review:

Building upon the success of the first edition, the Nuclear Engineering Handbook, Second Edition, provides a comprehensive, up-to-date overview of nuclear power engineering. Consisting of chapters written by leading experts, this volume spans a wide range of topics in the areas of nuclear power reactor design and operation, nuclear fuel cycles, and radiation detection. Plant safety issues are addressed, and the economics of nuclear power generation in the 21st century are presented. The Second Edition also includes full coverage of Generation IV reactor designs, and new information on MRS technologies, small modular reactors, and fast reactors.

Nuclear Corrosion Science and Engineering

Nuclear Corrosion Science and Engineering
Author: Damien FERON
Publsiher: Elsevier
Total Pages: 1072
Release: 2012-02-21
ISBN 10: 085709534X
ISBN 13: 9780857095343
Language: EN, FR, DE, ES & NL

Nuclear Corrosion Science and Engineering Book Review:

Corrosion of nuclear materials, i.e. the interaction between these materials and their environments, is a major issue for plant safety as well as for operation and economic competitiveness. Understanding these corrosion mechanisms, the systems and materials they affect, and the methods to accurately measure their incidence is of critical importance to the nuclear industry. Combining assessment techniques and analytical models into this understanding allows operators to predict the service life of corrosion-affected nuclear plant materials, and to apply the most appropriate maintenance and mitigation options to ensure safe long term operation. This book critically reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities. Initial sections introduce the complex field of nuclear corrosion science, with detailed chapters on the different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them. This is complemented by reviews of monitoring and control methodologies, as well as modelling and lifetime prediction approaches. Given that corrosion is an applied science, the final sections review corrosion issues across the range of current and next-generation nuclear reactors, and across such nuclear applications as fuel reprocessing facilities, radioactive waste storage and geological disposal systems. With its distinguished editor and international team of expert contributors, Nuclear corrosion science and engineering is an invaluable reference for nuclear metallurgists, materials scientists and engineers, as well as nuclear facility operators, regulators and consultants, and researchers and academics in this field. Comprehensively reviews the fundamental corrosion mechanisms that affect nuclear power plants and facilities Chapters assess different types of both aqueous and non aqueous corrosion mechanisms and the nuclear materials susceptible to attack from them Considers monitoring and control methodologies, as well as modelling and lifetime prediction approaches

Nuclear Thermal Hydraulic and Two Phase Flow

Nuclear Thermal Hydraulic and Two Phase Flow
Author: Jun Wang,Kaiyi Shi,Zhaoming Meng,Shripad T. Revankar
Publsiher: Frontiers Media SA
Total Pages: 329
Release: 2018-10-11
ISBN 10: 2889456129
ISBN 13: 9782889456123
Language: EN, FR, DE, ES & NL

Nuclear Thermal Hydraulic and Two Phase Flow Book Review:

Nuclear energy is one of the most important clear energy and contributes more than 10% electric power to human society in the past decades of years. The nuclear thermal hydraulic and two-phase flow is one of the basic branches of nuclear technology and provides structure design and safety analysis to the nuclear power reactors. In the new century, the basic theoretical research of thermal hydraulic and two-phase flow, and innovative design for the next generation nuclear power plants (especially for the small modular reactor and molten salt reactor), along with other nuclear branches, constantly support the development of nuclear technology.

Design basis Accident Analysis Methods For Light water Nuclear Power Plants

Design basis Accident Analysis Methods For Light water Nuclear Power Plants
Author: Robert Martin,Cesare Frepoli
Publsiher: World Scientific
Total Pages: 716
Release: 2019-02-13
ISBN 10: 9813275677
ISBN 13: 9789813275676
Language: EN, FR, DE, ES & NL

Design basis Accident Analysis Methods For Light water Nuclear Power Plants Book Review:

This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

TOP FUEL 2016

TOP FUEL 2016
Author: Anonim
Publsiher: Unknown
Total Pages: 329
Release: 2016
ISBN 10: 9780894487309
ISBN 13: 0894487302
Language: EN, FR, DE, ES & NL

TOP FUEL 2016 Book Review:

Energy Research Abstracts

Energy Research Abstracts
Author: Anonim
Publsiher: Unknown
Total Pages: 329
Release: 1983
ISBN 10:
ISBN 13: UOM:39015047745867
Language: EN, FR, DE, ES & NL

Energy Research Abstracts Book Review:

Advances in Molten Slags Fluxes and Salts

Advances in Molten Slags  Fluxes  and Salts
Author: Ramana Reddy,Pinakin Chaubal,P. Chris Pistorius,Uday Pal
Publsiher: Springer
Total Pages: 1373
Release: 2017-01-10
ISBN 10: 3319487698
ISBN 13: 9783319487694
Language: EN, FR, DE, ES & NL

Advances in Molten Slags Fluxes and Salts Book Review:

This collection focuses on ferrous and non-ferrous metallurgy where ionic melts, slags, fluxes, or salts play important roles in industrial growth and economy worldwide. Technical topics included are: thermodynamic properties and phase diagrams and kinetics of slags, fluxes, and salts; physical properties of slags, fluxes, and salts; structural studies of slags; interfacial and process phenomena involving foaming, bubble formation, and drainage; slag recycling, refractory erosion/corrosion, and freeze linings; and recycling and utilization of metallurgical slags and models and their applications in process improvement and optimization. These topics are of interest to not only traditional ferrous and non-ferrous metal industrial processes but also new and upcoming technologies.

Nuclear Reactor Physics

Nuclear Reactor Physics
Author: Weston M. Stacey
Publsiher: John Wiley & Sons
Total Pages: 766
Release: 2018-06-05
ISBN 10: 3527413669
ISBN 13: 9783527413669
Language: EN, FR, DE, ES & NL

Nuclear Reactor Physics Book Review:

The third, revised edition of this popular textbook and reference, which has been translated into Russian and Chinese, expands the comprehensive and balanced coverage of nuclear reactor physics to include recent advances in understanding of this topic. The first part of the book covers basic reactor physics, including, but not limited to nuclear reaction data, neutron diffusion theory, reactor criticality and dynamics, neutron energy distribution, fuel burnup, reactor types and reactor safety. The second part then deals with such physically and mathematically more advanced topics as neutron transport theory, neutron slowing down, resonance absorption, neutron thermalization, perturbation and variational methods, homogenization, nodal and synthesis methods, and space-time neutron dynamics. For ease of reference, the detailed appendices contain nuclear data, useful mathematical formulas, an overview of special functions as well as introductions to matrix algebra and Laplace transforms. With its focus on conveying the in-depth knowledge needed by advanced student and professional nuclear engineers, this text is ideal for use in numerous courses and for self-study by professionals in basic nuclear reactor physics, advanced nuclear reactor physics, neutron transport theory, nuclear reactor dynamics and stability, nuclear reactor fuel cycle physics and other important topics in the field of nuclear reactor physics.

Nuclear Safety in Light Water Reactors

Nuclear Safety in Light Water Reactors
Author: Bal Raj Sehgal
Publsiher: Academic Press
Total Pages: 714
Release: 2012
ISBN 10: 0123884462
ISBN 13: 9780123884466
Language: EN, FR, DE, ES & NL

Nuclear Safety in Light Water Reactors Book Review:

This vital reference is the only one-stop resource on how to assess, prevent, and manage severe nuclear accidents in the light water reactors (LWRs) that pose the most risk to the public. LWRs are the predominant nuclear reactor in use around the world today, and they will continue to be the most frequently utilized in the near future. Therefore, accurate determination of the safety issues associated with such reactors is central to a consideration of the risks and benefits of nuclear power. This book emphasizes the prevention and management of severe accidents, in order to teach nuclear professionals how to mitigate potential risks to the public to the maximum extent possible. Engineers, researchers, students and the personnel of vendors, safety authorities and nuclear power generation organizations require the knowledge offered by this volume's globally renowned experts to ensure they obtain a core competency in nuclear safety. Organizes and presents all the latest thought on LWR nuclear safety in one consolidated volume, provided by the top experts in the field, ensuring high-quality, credible and easily accessible information Explains how developments in the field of LWR severe accidents have provided more accurate determinations of risk, thereby shedding new light on the debates surrounding nuclear power safety, particularly in light of the recent tragedy in Japan Concentrates on prevention and management of accidents, developing methodologies to estimate the consequences and associated risks

An Introduction to Nuclear Waste Immobilisation

An Introduction to Nuclear Waste Immobilisation
Author: Michael I Ojovan,William E. Lee
Publsiher: Newnes
Total Pages: 376
Release: 2013-12-03
ISBN 10: 0080993931
ISBN 13: 9780080993935
Language: EN, FR, DE, ES & NL

An Introduction to Nuclear Waste Immobilisation Book Review:

Drawing on the authors’ extensive experience in the processing and disposal of waste, An Introduction to Nuclear Waste Immobilisation, Second Edition examines the gamut of nuclear waste issues from the natural level of radionuclides in the environment to geological disposal of waste-forms and their long-term behavior. It covers all-important aspects of processing and immobilization, including nuclear decay, regulations, new technologies and methods. Significant focus is given to the analysis of the various matrices used, especially cement and glass, with further discussion of other matrices such as bitumen. The final chapter concentrates on the performance assessment of immobilizing materials and safety of disposal, providing a full range of the resources needed to understand and correctly immobilize nuclear waste. The fully revised second edition focuses on core technologies and has an integrated approach to immobilization and hazards Each chapter focuses on a different matrix used in nuclear waste immobilization: cement, bitumen, glass and new materials Keeps the most important issues surrounding nuclear waste - such as treatment schemes and technologies and disposal - at the forefront

Sustainable and Safe Nuclear Fission Energy

Sustainable and Safe Nuclear Fission Energy
Author: Günter Kessler
Publsiher: Springer Science & Business Media
Total Pages: 466
Release: 2012-05-08
ISBN 10: 3642119905
ISBN 13: 9783642119903
Language: EN, FR, DE, ES & NL

Sustainable and Safe Nuclear Fission Energy Book Review:

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.