The Proceedings of the National Symposium on Power and Energy Systems
Online ISSN : 2424-2950
2007.12
Session ID : OS8-6
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OS8-6 Status and Prospect of Development of Lead-alloy-cooled Fast Reactor
Minoru TAKAHASHIHiroshi SEKIMOTO
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CONFERENCE PROCEEDINGS FREE ACCESS

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Abstract
The status and prospect of lead alloy-cooled fast reactor (LFR) have been explained for future development of various types of LFRs that will be required for sustainable development of the world. Advantages of the LFRs compared with sodium-cooled fast reactors (SFR) are emphasized based on inherently safe characteristics of the LFRs. Topics of research studies for the development of LFRs, e.g., compatibility of materials with lead alloy, oxygen control technique, have been described referring recent studies.
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© 2007 The Japan Society of Mechanical Engineers
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