Reactor G 1

Reactor G 1

Author: France. Commissariat à l'énergie atomique. Département des études de piles

Publisher:

Published: 1962

Total Pages: 378

ISBN-13:

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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.


NAA-SR.

NAA-SR.

Author: U.S. Atomic Energy Commission

Publisher:

Published: 1958

Total Pages: 216

ISBN-13:

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Basic Studies in the Field of High-temperature Engineering

Basic Studies in the Field of High-temperature Engineering

Author: Nihon Genshiryoku Kenkyūjo

Publisher: Paris, France : Nuclear Energy Agency, Organisation for Economic Co-operation and Development

Published: 2002

Total Pages: 370

ISBN-13:

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In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the NEA organised a Second Information Exchange Meeting on Basic Studies in the Field of High-temperature Engineering. These proceedings provide an overview of the activities being carried out in eight countries, the improvement of material properties for HTGR application, in-core monitoring methods and properties of irradiated graphite, and HTGR fuel fabrication and performance.