Advances in High Temperature Gas Cooled Reactor Fuel Technology
Advances in High Temperature Gas Cooled Reactor Fuel Technology

Author: International Atomic Energy Agency

Publisher:

Published: 2012-06

Total Pages: 639

ISBN-13: 9789201253101

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This publication reports on the results of a coordinated research project on advances in high temperature gas cooled reactor (HTGR) fuel technology and describes the findings of research activities on coated particle developments. These comprise two specific benchmark exercises with the application of HTGR fuel performance and fission product release codes, which helped compare the quality and validity of the computer models against experimental data. The project participants also examined techniques for fuel characterization and advanced quality assessment/quality control. The key exercise included a round-robin experimental study on the measurements of fuel kernel and particle coating properties of recent Korean, South African and US coated particle productions applying the respective qualification measures of each participating Member State. The summary report documents the results and conclusions achieved by the project and underlines the added value to contemporary knowledge on HTGR fuel.

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.

Canada Enters the Nuclear Age
Canada Enters the Nuclear Age

Author: Atomic Energy of Canada Limited

Publisher: McGill-Queen's Press - MQUP

Published: 1997

Total Pages: 466

ISBN-13: 9780773516014

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The nuclear energy company has overseen the production of its own history, focusing on programs at its laboratories in Chalk River, Ontario, and Whiteshell, Manitoba between 1943 and 1985. The 16 scientists who wrote the narrative discuss the organization and operations of the laboratories, nuclear safety and radiation protection, radioisotopes, basic research, developing the CANDU reactor, managing the radioactive wastes, business development, and revenue generation. Canadian card order number: C97-900188-9. Annotation copyrighted by Book News, Inc., Portland, OR

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.

Uranium Extraction Technology
Uranium Extraction Technology

Author: International Atomic Energy Agency

Publisher:

Published: 1993

Total Pages: 384

ISBN-13:

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The purpose of this publication is to update and expand the first edition, which was published in 1983, and to report on later advances in uranium ore processing. It includes background information about the principles of the unit operations used in uranium ore processing and summarizes the current state of the art. Extensive references provide sources for specific technological details.

Characterization and Testing of Materials for Nuclear Reactors
Characterization and Testing of Materials for Nuclear Reactors

Author: International Atomic Energy Agency

Publisher:

Published: 2007

Total Pages: 158

ISBN-13:

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Industrial growth, energy consumption are seen as measures towards economic developments. With increase in industrial development worldwide, the demand of energy is continually on the rise. Today, the energy industry is facing many challenges. Nuclear fission and nuclear fusion are seen as important future energy sources. Development of innovative reactor designs with large efficiency for fuel burn up is one of the needs of fission reactors. The materials resistant to high dose of radiations in fusion reactors is another major challenge. The production of electricity without global warming is an important pressing demand on the energy sector. The demands on quality control of components for nuclear and heavy industry are very stringent. Development of well characterized, high quality materials is therefore essential for safe, efficient and reliable operation of engineering components. The diagnosis of failure of machinery parts comes from the post operational characterization of materials. Various destructive and non-destructive techniques are used for this purpose. Research reactors have played an important role in non-destructive characterization of materials and have contributed to technology development. This publication focuses on characterization of materials for industries in general and nuclear energy sector in particular. The main focus is on research reactor based techniques with some discussion on other allied methods like positron annihilation.--Publisher's description.

Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions
Modelling of Fuel Behaviour in Design Basis Accidents and Design Extension Conditions

Author: International Atomic Energy Agency

Publisher:

Published: 2020-07-30

Total Pages: 218

ISBN-13: 9789201080202

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This publication is the result of an IAEA technical meeting and reports on Member States' capabilities in modelling, predicting and improving their understanding of the behaviour of nuclear fuel under accident conditions. The main results and outcomes of a coordinated research project (CRP) on this topic are also presented.

Pellet-clad Interaction in Water Reactor Fuels
Pellet-clad Interaction in Water Reactor Fuels

Author:

Publisher: OECD Publishing

Published: 2005

Total Pages: 562

ISBN-13:

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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.