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

Sergey Smolentsev; Tyler Rhodes; Gautam Pulugundla; Cyril Courtessole; Mohamed Abdou; Siegfried Malang; Mark Tillack; Chuck Kessel

doi:10.1016/j.fusengdes.2017.06.017

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

Sergey Smolentsev, Tyler Rhodes, Gautam Pulugundla, Cyril Courtessole, Mohamed Abdou, Siegfried Malang, Mark Tillack, Chuck Kessel

Research output: Contribution to journal › Article › peer-review

35 Scopus citations

Abstract

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.

Original language	English
Pages (from-to)	314-323
Number of pages	10
Journal	Fusion Engineering and Design
Volume	135
DOIs	https://doi.org/10.1016/j.fusengdes.2017.06.017
State	Published - Oct 2018
Externally published	Yes

Funding

The authors from UCLA acknowledge the support from the US Department of Energy, Office of Fusion Energy Sciences, under Grant # DE-FG02-86ER52123. We appreciate continuous discussions and valuable support over the entire course of the studies from Laila El-Guebaly and Edward Marriott from the University of Wisconsin. The authors from UCLA acknowledge the support from the US Department of Energy, Office of Fusion Energy Sciences , under Grant # DE-FG02-86ER52123 . We appreciate continuous discussions and valuable support over the entire course of the studies from Laila El-Guebaly and Edward Marriott from the University of Wisconsin.

Funders	Funder number
Office of Fusion Energy Sciences	DE-FG02-86ER52123
US Department of Energy
University of Wisconsin-Madison
University of California, Los Angeles

Keywords

Blanket
DCLL
FNSF
Lead-lithium
Magnetohydrodynamics
Pressure drop

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2017.06.017

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abstract = "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.",

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

Abstract

Funding

Keywords

UN SDGs

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