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Advanced Fuel Pellet Materials and Fuel Rod Design for Water Cooled Reactors

IAEA TECDOC No. 1654
English IAEA-TECDOC-1654 978-92-0-108910-6
240 18.00 2010

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Description

This publication is the proceedings of a technical meeting on enhancement of efficiency of nuclear power through increased fuel utilization and better performance. It provides an overview of the current status in the development of fuel pellet material and of improvements in fuel rod designs for light and heavy water cooled power reactors. The meeting participants focused their discussions on modern technological and design tools enabling reliable fuel performance in current and planned operational environments, analysed high burn-up fuel structure and properties as well as specific features of advanced fuels. In addition, there was a round-table discussion that addressed the regulatory aspects of fuel quality assurance.

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