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Plan for IEA LB Workshop

The IEA Liquid Breeder Blanket Workshop, held at UCLA from August 2-4, 2010, aimed to enhance collaboration among IEA parties on liquid breeding technology. Key goals included sharing recent R&D results, discussing future R&D plans, and focusing on tritium interaction, recovery, and control in LiPb. With uncertainties in tritium solubility and efficiency still prevalent, the workshop featured sessions on production, characterization, transport properties, and safety concerns. This international collaboration is vital for advancing research and development in fusion technology.

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Plan for IEA LB Workshop

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  1. Plan for IEA LB Workshop Dai-Kai Sze, UCSD PattrickCalderoni, INL Fusion Nuclear Science and Technology Meeting UCLA, August 2-4, 2010

  2. Goal for the Workshop • Exchange of information among IEA Parties on liquid breeder blanket technology. • Offer a timely opportunity to exchange and discuss most recent results being generated through on going R&D efforts. • Discuss future R/D plans and possible collaborated R/D activities.

  3. Key technical area for discussion • It was agreed upon that tritium interaction with LiPb, tritium recovery and tritium control are the technical areas with most common interest. • As of 2007, the uncertainty of tritium solubility in LiPb is 4 order of magnitude. • Based on recent work from US and Japan, this uncertainty has been reduced to within a facor of 10. • Tritium recovery efficiency has not reached design value of ~90%

  4. Workshop Program • Session 1 IEA parties R&D liquid metal breeding blanket program. • Session 2 LiPb production and characterization • Session 3 Tritium transport properties in LiPb eutectic. • Session 4 Tritium control and sensing technologies.

  5. Workshop program (II) • Session 5 Insulating, anti-corrosion and anti-permeation barriers development. • Session 6 Safety, irradiation issues and nuclear data. • Session 7 Mathematical model development • Session 8 Test program on the LiPb breeder blankets development: ITER TBM and role of IFMIF.

  6. Future NTFR IA research topics • Tritium recovery • Tritium solubility • Corrosion • Tritium permeation coating development • MHD • Code developement

  7. Benefit to US program • There are many issues associated with LiPb blankets. • US FNST does not have sufficient resource to obtain all the necessary data. • International collaboration is a way to share the effort and also share the results. • Our strength are in the areas of tritium interaction, MHD and code development.

  8. Conclusion • The IEA workshop on liquid breeder is to discuss future collaboration on liquid breeder based on LiPb. • A good collaboration will be beneficial to all the parties. • The total number of participants to this workshop will be more than 50, with about 8 people from US. • The R/D programs to be discussed in this workshop, will provide required data base for the TBM programs.

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