Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic

IAEA Nuclear Energy Series No. NP-T-1.6

Subject Classification: 0703-Reactor technology

English STI/PUB/1567; (ISBN:978-92-0-131810-7); 82 pp.; 25 figures; € 25.00; Date Published: 2012

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The choice of the coolant is one of the main technical issues concerning fast reactor design, since it determines design approach as well as safety, technical and economic characteristics of the system. This publication provides a comprehensive summary of the status of the liquid metal coolant technology development for fast reactors with regard to basic data and main technological challenges. It starts with remarks on the history of nuclear power development, provides a complete survey of physical and chemical properties of liquid metals, and discusses the coolant quality control and thermal-hydraulics studies for both sodium and lead alloys systems. Other chapters elaborate on radioactivity of coolants and describe past experiences as well as current projects. Finally, the design objectives, and main research and technology development challenges of innovative fast reactors having sodium, lead-bismuth eutectic, and lead as coolant, currently under investigation in the Russian Federation, as well as the status of the respective research and development activities, are summarized.

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