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LOCATION:HG F 26.3
DTSTART;TZID=Europe/Stockholm:20240603T153000
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UID:submissions.pasc-conference.org_PASC24_sess105_msa290@linklings.com
SUMMARY:Computational Magnetohydrodynamics (CMHD) – Recent Progress and Fu
 ture Directions for Fusion
DESCRIPTION:Minisymposium\n\nSergey Smolentsev (Oak Ridge National Laborat
 ory)\n\nIn a fusion reactor  sub-system called blanket, a liquid breeder (
 liquid metal LM or molten salt MS) flows for tritium breeding and conversi
 on of plasma energy into heat. LM flows in the fusion blanket are strongly
  affected by the plasma-confining magnetic field and volumetric heating th
 at drastically change the flow behavior and modify associated  transport p
 rocesses. Predicting magnetohydrodynamic (MHD) flows, corrosion, and triti
 um transport is critically important to any LM blanket design. The computa
 tional magnetohydrodynamic (CMHD) tools have been successfully used by fus
 ion researchers to assist in the blanket design and analysis since the fir
 st computations in 1970’s. However, for decades, the applicability of thes
 e tools was limited to relatively simple geometries, low flow velocities a
 nd low to moderate magnetic fields. This paper overviews recent progress a
 nd future directions in the CMHD area for fusion with the main focus on th
 e existing and new CMHD codes, numerical methods, and applications. Two ex
 amples presented in the paper, high magnetic field lead-lithium blanket, a
 nd integrated computer modelling for the Dual Coolant Lead Lithium (DCLL) 
 blanket, evidence that the CMHD codes are reaching the stage where they ca
 n be used as a real design tool.\n\nDomain: Engineering, Physics, Computat
 ional Methods and Applied Mathematics\n\nSession Chair: Franklin Curtis (O
 ak Ridge National Laboratory)
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