MHD Analysis of Dual-Coolant Lead-Lithium Blanket for Spherical Tokamak Advanced Reactor

Gupta, Deepa; Brooks, Arthur; Brown, Thomas; Khodak, Andrei; Linn, Brian; Menard, Jonathan

doi:10.1080/15361055.2025.2560740

MHD Analysis of Dual-Coolant Lead-Lithium Blanket for Spherical Tokamak Advanced Reactor

Journal Article · Thu Oct 02 00:00:00 EDT 2025 · Fusion Science and Technology

DOI:https://doi.org/10.1080/15361055.2025.2560740· OSTI ID:2999371

^[1]; Brooks, Arthur ^[1]; ^[1]; ^[1]; Linn, Brian ^[1]; ^[1]

Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

The tritium breeding blanket is vital for future fusion power plants, with the Spherical Tokamak Advanced Reactor (STAR) project highlighting the dual-coolant lead-lithium (DCLL) design. The DCLL blanket performs shielding, energy exhaust, and tritium breeding using a lead-lithium alloy , with lithium as the breeder and lead as the neutron multiplier. It also serves as the primary coolant, with helium providing supplemental cooling. Reduced-activation ferritic/martensitic steel is used for the blanket structure. Magnetohydrodynamic (MHD) phenomena influence the liquid metal flow in a magnetic field, affecting heat transfer in the breeder affected by energetic neutrons. Understanding key flow parameters in such conditions is critical for efficient DCLL design. This study uses three-dimensional thermofluid MHD analysis with ANSYS CFX software, modified at Princeton Plasma Physics Laboratory, to simulate high Hartmann flows. The neutronics code MCNP, coupled with plasma equilibrium, provides heat source distribution. In conclusion, we examine electromagnetic interactions in adjacent fluid domains and analyze the magnetic field’s impact on flow distribution in the inboard and outboard blanket layout, using detailed mesh generation for accurate results.

View Accepted Manuscript (DOE)

Research Organization:: Princeton Plasma Physics Laboratory (PPPL), Princeton, NJ (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC02-09CH11466

OSTI ID:: 2999371

Journal Information:: Fusion Science and Technology, Journal Name: Fusion Science and Technology; ISSN 1943-7641; ISSN 1536-1055

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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