Dual-coolant lead-lithium (DCLL) blanket status and R&D needs

作者：Smolentsev Sergey^*; Morley Neil B; Abdou Mohamed A; Malang Siegfried

来源：Fusion Engineering and Design, 2015, 100: 44-54.

DOI：10.1016/j.fusengdes.2014.12.031

• DCLL blanket
• R& D
• Test facilities
• MHD
• Liquid metal
• Lead-lithium

The DCLL is an attractive breeding blanket concept that leads to a high-temperature (T similar to 700 degrees C), high thermal efficiency (eta > 40%) blanket system. The key element of the concept is a flow channel insert (FCI) that serves as an electrical and thermal insulator to reduce the magnetohydrodynamic (MHD) pressure drop and to decouple the temperature-limited RAFM (reduced-activation ferritic/martensitic) steel wall from the flowing hot PbLi. The paper introduces the concept, reviews history of the development of the DCLL in the US and worldwide and then identifies critical R&D needs prior to fusion environment testing in four research areas important to the successful development of the DCLL concept: (1) PbLi MHD thermofluids, (2) fluid materials interaction, (3) tritium transport, and (4) FCI development and characterization. For these areas, the most important R&D results obtained in the US in the ITER DCLL TBM program (2005-2011) and more recently are reviewed, including experimental and computational studies of MHD PbLi flows, corrosion of RAFM, tritium permeation, and silicon carbide FCI fabrication and material qualification. We also discuss required features of non-fusion facilities for DCLL blanket testing, where current lab experiments and modeling could progress to multiple effects and partially-integrated studies that approach as nearly as possible prototypic, integrated blanket conditions prior to testing in a fusion environment.

• 出版日期2015-11