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

Author:

Publisher:

Published: 2018

Total Pages: 148

ISBN-13:

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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.


Thorium Fuel Cycle

Thorium Fuel Cycle

Author: International Atomic Energy Agency

Publisher:

Published: 2005

Total Pages: 120

ISBN-13:

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Provides a critical review of the thorium fuel cycle: potential benefits and challenges in the thorium fuel cycle, mainly based on the latest developments at the front end of the fuel cycle, applying thorium fuel cycle options, and at the back end of the thorium fuel cycle.


Status and Trends in Spent Fuel Reprocessing

Status and Trends in Spent Fuel Reprocessing

Author: International Atomic Energy Agency

Publisher: IAEA

Published: 2005

Total Pages: 116

ISBN-13:

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The management of spent fuel arising from nuclear power production is a crucial issue for the sustainable development of nuclear energy. The IAEA has issued several publications in the past that provide technical information on the global status and trends in spent fuel reprocessing and associated topics, and one reason for this present publication is to provide an update of this information which has mostly focused on the conventional technology applied in the industry. However, the scope of this publication has been significantly expanded in an attempt to make it more comprehensive and by including a section on emerging technologies applicable to future innovative nuclear systems, as are being addressed in such international initiatives as INPRO, Gen IV and MICANET. In an effort to be informative, this publication attempts to provide a state-of-the-art review of these technologies, and to identify major issues associated with reprocessing as an option for spent fuel management. It does not, however, provide any detailed information on some of the related issues such as safety or safeguards, which are addressed in other relevant publications.


The EBR-II Fuel Cycle Story

The EBR-II Fuel Cycle Story

Author: Charles E. Stevenson

Publisher:

Published: 1987

Total Pages: 274

ISBN-13:

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In this comprehensive volume, Stevenson recounts the history of the Experimental Breeder Reactor-II (EBR-II), the Fuel Cycle Facility (FCF), and the process requirements of this unique technology. The author also explains the reasons behind the remarkable success of both the EBR-II and the FCF. These data, presented as a useful information source, should be of considerable significance to the continuing development of nuclear power.


Nuclear Corrosion Science and Engineering

Nuclear Corrosion Science and Engineering

Author: Damien Feron

Publisher: Elsevier

Published: 2012-02-21

Total Pages: 1073

ISBN-13: 085709534X

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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


The Chemistry of the Actinide and Transactinide Elements (3rd ed., Volumes 1-5)

The Chemistry of the Actinide and Transactinide Elements (3rd ed., Volumes 1-5)

Author: L.R. Morss

Publisher: Springer Science & Business Media

Published: 2007-12-31

Total Pages: 4059

ISBN-13: 1402035985

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The Chemistry of the Actinide and Transactinide Elements is a contemporary and definitive compilation of chemical properties of all of the actinide elements, especially of the technologically important elements uranium and plutonium, as well as the transactinide elements. In addition to the comprehensive treatment of the chemical properties of each element, ion, and compound from atomic number 89 (actinium) through to 109 (meitnerium), this multi-volume work has specialized and definitive chapters on electronic theory, optical and laser fluorescence spectroscopy, X-ray absorption spectroscopy, organoactinide chemistry, thermodynamics, magnetic properties, the metals, coordination chemistry, separations, and trace analysis. Several chapters deal with environmental science, safe handling, and biological interactions of the actinide elements. The Editors invited teams of authors, who are active practitioners and recognized experts in their specialty, to write each chapter and have endeavoured to provide a balanced and insightful treatment of these fascinating elements at the frontier of the periodic table. Because the field has expanded with new spectroscopic techniques and environmental focus, the work encompasses five volumes, each of which groups chapters on related topics. All chapters represent the current state of research in the chemistry of these elements and related fields.


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.