WPFC Expert Group on Heavy Liquid Metal Technologies (WPFC/HLM)

EGHLM mandate


Lead-bismuth eutectic (LBE) is a very effective nuclear coolant because of its low melting temperature, high boiling temperature and neutronic transparency. In addition, LBE itself is a very efficient spallation target for neutron generation via a high-energy proton accelerator. On the other hand, liquid metal corrosion and embrittlement are major issues that must be dealt with in using LBE as a nuclear coolant and spallation target. Thus, LBE continues to be the subject of considerable research in the U.S, Europe and Asia, specifically within the framework of the accelerator-driven transmutation systems and fast-spectrum reactors. An expert group that addresses the major issues associated with the use of LBE as a nuclear coolant in a unified framework would be of benefit to all the interested parties. The main deliverable of the expert group is the LBE handbook.


The objectives of the Expert Group are:


A number of new HLM experiments are underway in Europe, such as the EUROTRANS project (devoted to the study of high level nuclear waste transmutation with sub-critical accelerator driven systems) and the ELSY project (devoted to the development of an HLM cooled critical transmutation system). 
Moreover additional new experimental results are expected from laboratories in Japan, USA and Korea. These new experimental results will be crucial to consolidate:

Finally, the successful completion of the MEGAPIE experiment will deliver unique results on materials behaviour in HLM and representative conditions of a high power neutron spallation target. The consolidation of the understanding of HLM properties, the materials and thermal-hydraulics assessment, as well as the technological advancement, will be an essential contribution to the development of selected Gen-IV fast reactors / radioactive waste transmuters.


Related documents are in members' working area (requires password).


Related links

Working Party on Scientific Issues of the Fuel Cycle (WPFC)

Benchmarking of Thermal-Hydraulic Loop Models for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)

Workshop on Structural Materials for Innovative Nuclear Systems (SMINS-3)

Members' working area (requires password)



For more information on this working party, please contact  (Tel: +33 1 45 24 10 82)

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Last updated: 3 April 2015