Nuclear Safety

Nuclear Safety

Author: Gianni Petrangeli

Publisher: Elsevier

Published: 2006-05-30

Total Pages: 447

ISBN-13: 008046078X

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Nuclear Safety provides the methods and data needed to evaluate and manage the safety of nuclear facilities and related processes using risk-based safety analysis, and provides readers with the techniques to assess the consequences of radioactive releases. The book covers relevant international and regional safety criteria (US, IAEA, EUR, PUN, URD, INI). The contents deal with each of the critical components of a nuclear plant, and provide an analysis of the risks arising from a variety of sources, including earthquakes, tornadoes, external impact and human factors. It also deals with the safety of underground nuclear testing and the handling of radioactive waste. - Covers all plant components and potential sources of risk including human, technical and natural factors. - Brings together information on nuclear safety for which the reader would previously have to consult many different and expensive sources. - Provides international design and safety criteria and an overview of regulatory regimes.


Molten Salts

Molten Salts

Author: Marcelle Gaune-Escard

Publisher: Springer Science & Business Media

Published: 2002-01-31

Total Pages: 426

ISBN-13: 9781402004599

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Intending these truncated proceedings of the May 2001 meeting to serve as a textbook rather than an ordinary proceedings volume, Gaune-Escard (Institut Universitaire des Systemes Thermiques Industriels, France) presents 16 papers topics of molten salts including electronic properties, light and neutron scattering, thermodynamic modeling, pyrochemistry in the nuclear industry, electrochemical techniques, and molten salt batteries. Annotation (c)2003 Book News, Inc., Portland, OR (booknews.com).


Proceedings of the Workshop on Pyrochemical Separations

Proceedings of the Workshop on Pyrochemical Separations

Author: Workshop on Pyrochemical Separations

Publisher:

Published: 2001

Total Pages: 336

ISBN-13: 9786610034284

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The industrial treatment of spent nuclear fuel is presently performed using different wet chemical processes. Alternative dry processes, using pyrochemical methods, have received some attention due to their potential advantages in terms of plant design and criticality safety, as well as radiation dose. Recent progress in the transmutation of long-lived fission products and minor actinides has brought renewed interest in pyrochemical methods, as effective transmutation will be based on multi-recycling of the fuel with very high burn-up and short cooling times, conditions under which pyrochemic.


Status of Fast Reactor Research and Technology Development

Status of Fast Reactor Research and Technology Development

Author: International Atomic Energy Agency

Publisher:

Published: 2012

Total Pages: 0

ISBN-13: 9781523130191

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"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.


Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Viability of Inert Matrix Fuel in Reducing Plutonium Amounts in Reactors

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2006

Total Pages: 100

ISBN-13:

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The reactors around the world have produced more than 2000 tonnes of plutonium, contained in spent fuel or as separated forms through reprocessing. Disposition of fissile materials has become a primary concern of nuclear non-proliferation efforts worldwide. There is a significant interest in IAEA Member States to develop proliferation resistant nuclear fuel cycles for incineration of plutonium such as inert matrix fuels (IMFs). This publication reviews the status of potential IMF candidates and describes several identified candidate materials for both fast and thermal reactors: MgO, ZrO2, SiC, Zr alloy, SiAl, ZrN; some of these have undergone test irradiations and post irradiation examination. Also discussed are modelling of IMF fuel performance and safety analysis. System studies have identified strategies for both implementation of IMF fuel as homogeneous or heterogeneous phases, as assemblies or core loadings and in existing reactors in the shorter term, as well as in new reactors in the longer term.