MHD thermohydraulics analysis and supporting R&D for DCLL blanket in the FNSF

A Fusion Nuclear Science Facility (FNSF) has been recognized in the fusion community as a necessary facility to resolve the critical technology issues of in-vessel components prior to the construction of a DEMO reactor (Abdou et al., 1996) [1]. Among these components, development of a reliable, low-...

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Bibliographic Details
Published in:Fusion engineering and design 2018-10, Vol.135, p.314-323
Main Authors: Smolentsev, Sergey, Rhodes, Tyler, Pulugundla, Gautam, Courtessole, Cyril, Abdou, Mohamed, Malang, Siegfried, Tillack, Mark, Kessel, Chuck
Format: Article
Language:English
Subjects:
Blanket
Configuration management
DCLL
Design
Design analysis
Electrical raceways
Fluid mechanics
FNSF
Fusion
Lead-lithium
Lithium
Magnetohydrodynamics
Nuclear fusion
Nuclear power plants
Nuclear security
Pressure drop
R&D
Research & development
Thermohydraulics
Tritium
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Summary:A Fusion Nuclear Science Facility (FNSF) has been recognized in the fusion community as a necessary facility to resolve the critical technology issues of in-vessel components prior to the construction of a DEMO reactor (Abdou et al., 1996) [1]. Among these components, development of a reliable, low-cost and safe blanket system that provides self-sufficient tritium breeding and efficient conversion of the extracted fusion energy to electricity, while meeting all material, design and configuration limitations is among the most important but still challenging goals. In the recent FNSF study in the US (Kesel et al., 2015) [2], a Dual-Coolant Lead-Lithium (DCLL) blanket has been selected as the main breeding blanket concept. This paper summarizes the most important details of the proposed DCLL blanket design, presents the MHD thermohydraulic analysis for the PbLi flows in the blanket conduits and introduces supporting R&D studies, which are presently ongoing at UCLA. We also discuss the required pre-FNSF R&D in the area of MHD Thermofluids to support the further work on the DCLL blanket design & analysis and its integration into the fusion facility.
ISSN:0920-3796
1873-7196
DOI:10.1016/j.fusengdes.2017.06.017