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Zirconium in the Nuclear Industry: Tenth International Symposium

Zirconium in the Nuclear Industry: Tenth International Symposium PDF Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805

Book Description


Zirconium in the Nuclear Industry: Tenth International Symposium

Zirconium in the Nuclear Industry: Tenth International Symposium PDF Author: A. M. Garde
Publisher: ASTM International
ISBN: 0803120117
Category : Nuclear fuel claddings
Languages : en
Pages : 805

Book Description


Scientific Issues in Fuel Behaviour

Scientific Issues in Fuel Behaviour PDF Author: NEA Nuclear Science Committee. Task Force on Scientific Issues Related to Fuel Behaviour
Publisher: OECD
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 96

Book Description
Dated January 1995

Urban Resilience for Emergency Response and Recovery

Urban Resilience for Emergency Response and Recovery PDF Author: Gian Paolo Cimellaro
Publisher: Springer
ISBN: 3319306561
Category : Science
Languages : en
Pages : 535

Book Description
This book introduces the concepts of Resilience-Based Design (RBD) as an extension of Performance-Based Design. It provides readers with a range of cutting-edge methodologies for evaluating resilience and clarifies the difference between resilience, vulnerability and sustainability. Initially, the book focuses on describing the different types of uncertainty that arise in the context of resilience evaluation. This is followed by an entire chapter dedicated to the analytical and experimental recovery functions. Then, starting from the definition of resilience provided by MCEER, an extension of the methodology is provided that introduces the seven dimensions of Community Resilience, summarized in the acronym PEOPLES. They are: Population and Demographics, Environmental/Ecosystem, Organized Governmental Services, Physical infrastructures, Lifestyle and Community Competence, Economic Development, and Socio-Cultural Capital. For each dimension, components and subcomponents are defined and the related indices are provided. Underlining the importance of the physical infrastructure dimension, the book provides several examples of applications for transportation, hydraulic, gas and power networks. The problem of interdependencies and the domino effect is also taken into account during the analysis. One of the book’s closing chapters focuses on different methodologies for improving disaster preparedness and engineering mitigation strategies, while the last chapter describes the different computer platforms available on the market for evaluating Community Resilience. The book offers readers an extensive introduction to the concept of Resilience-Based Design, together with selected advanced applications for specialists. No prerequisite knowledge is needed in order to understand the book, and the Appendix offers valuable supplemental information on e.g. the probabilistic concepts. As such, the book offers a valuable resource for graduate students, young engineers and researchers who are interested in the topic, and can also be used as a supplementary text in graduate level Disaster Resilience courses.

Fuel Modelling in Accident Conditions

Fuel Modelling in Accident Conditions PDF Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201639196
Category : Technology & Engineering
Languages : en
Pages : 180

Book Description
This publication summarizes the findings and conclusions of an IAEA coordinated research project (CRP) on fuel modelling in accident conditions, which was initiated under the IAEA Action Plan on Nuclear Safety following the Fukushima accident. The overall aim of the project was to analyse and better understand fuel behavior in accident conditions, with a focus on loss of coolant accidents. In the course of the project the participants used a mixture of data derived from accident simulation experiments, in particular data designed to investigate the fuel behaviour during design basis accident and design extension conditions. They carried out calculations on priority cases selected from a matrix of cases identified at the first research coordination meeting and designed to support their individual priorities. These priority cases were chosen as the best available to help determine which of the many models used in the codes best reflect reality. The CRP provided an ideal platform to compare their code results with others and especially with experimental data, to which they otherwise would not have had access. The achievements made within this CRP fostered new collaborations and enhanced the development and improvement of common models and highlighted differences in the interpretation of some experiments and therefore in the use of the codes ? the so-called user effects.

Nuclear Back-end and Transmutation Technology for Waste Disposal

Nuclear Back-end and Transmutation Technology for Waste Disposal PDF Author: Ken Nakajima
Publisher: Springer
ISBN: 4431551115
Category : Technology & Engineering
Languages : en
Pages : 331

Book Description
This book covers essential aspects of transmutation technologies, highlighting especially the advances in Japan. The accident at the Fukushima Daiichi Nuclear Power Plant (NPP) has caused us to focus attention on a large amount of spent nuclear fuels stored in NPPs. In addition, public anxiety regarding the treatment and disposal of high-level radioactive wastes that require long-term control is growing. The Japanese policy on the back-end of the nuclear fuel cycle is still unpredictable in the aftermath of the accident. Therefore, research and development for enhancing the safety of various processes involved in nuclear energy production are being actively pursued worldwide. In particular, nuclear transmutation technology has been drawing significant attention after the accident. This publication is timely with the following highlights: 1) Development of accelerator-driven systems (ADSs), which is a brand-new reactor concept for transmutation of highly radioactive wastes; 2) Nuclear reactor systems from the point of view of the nuclear fuel cycle. How to reduce nuclear wastes or how to treat them including the debris from TEPCO’s Fukushima nuclear power stations is discussed; and 3) Environmental radioactivity, radioactive waste treatment and geological disposal policy. State-of-the-art technologies for overall back-end issues of the nuclear fuel cycle as well as the technologies of transmutation are presented here. The chapter authors are actively involved in the development of ADSs and transmutation-related technologies. The future of the back-end issues in Japan is very uncertain after the accident at the Fukushima Daiichi NPP and this book provides an opportunity for readers to consider the future direction of those issues.

Nuclear Power Plant Design and Analysis Codes

Nuclear Power Plant Design and Analysis Codes PDF Author: Jun Wang
Publisher: Woodhead Publishing
ISBN: 0128181915
Category : Technology & Engineering
Languages : en
Pages : 612

Book Description
Nuclear Power Plant Design and Analysis Codes: Development, Validation, and Application presents the latest research on the most widely used nuclear codes and the wealth of successful accomplishments which have been achieved over the past decades by experts in the field. Editors Wang, Li,Allison, and Hohorst and their team of authors provide readers with a comprehensive understanding of nuclear code development and how to apply it to their work and research to make their energy production more flexible, economical, reliable and safe.Written in an accessible and practical way, each chapter considers strengths and limitations, data availability needs, verification and validation methodologies and quality assurance guidelines to develop thorough and robust models and simulation tools both inside and outside a nuclear setting. This book benefits those working in nuclear reactor physics and thermal-hydraulics, as well as those involved in nuclear reactor licensing. It also provides early career researchers with a solid understanding of fundamental knowledge of mainstream nuclear modelling codes, as well as the more experienced engineers seeking advanced information on the best solutions to suit their needs. - Captures important research conducted over last few decades by experts and allows new researchers and professionals to learn from the work of their predecessors - Presents the most recent updates and developments, including the capabilities, limitations, and future development needs of all codes - Incudes applications for each code to ensure readers have complete knowledge to apply to their own setting

Pellet-clad Interaction in Water Reactor Fuels

Pellet-clad Interaction in Water Reactor Fuels PDF Author:
Publisher: OECD Publishing
ISBN:
Category : Business & Economics
Languages : en
Pages : 562

Book Description
This publication sets out the findings of an international seminar, held in Aix-en-Provence, France in March 2004, which considered recent progress in the field of pellet-clad interaction in light water reactor fuels. It also reviews current understanding of relevant phenomena and their impact on the nuclear fuel rod under the widest possible conditions, and about both uranium-oxide and mixed-oxide fuels.

Handbook of Nuclear Engineering

Handbook of Nuclear Engineering PDF Author: Dan Gabriel Cacuci
Publisher: Springer Science & Business Media
ISBN: 0387981306
Category : Science
Languages : en
Pages : 3701

Book Description
This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Nuclear Fuel Safety Criteria

Nuclear Fuel Safety Criteria PDF Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 74

Book Description
Presents brief descriptions of 20 fuel-related safety criteria along with both the rationale for having such criteria and possible new design and operational issues which could have an effect on them.

State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry

State-of-the-art Report on the Progress of Nuclear Fuel Cycle Chemistry PDF Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 148

Book Description
The implementation of advanced nuclear systems requires that new technologies associated with the back end of the fuel cycle are developed. The separation of minor actinides from other fuel components is one of the advanced concepts being studied to help close the nuclear fuel cycle and to improve the long-term effects on the performance of geological repositories. Separating spent fuel elements and subsequently converting them through transmutation into short-lived nuclides should considerably reduce the longterm risks associated with nuclear power generation.