3D thermo-fluid MHD simulation of single straight channel flow in LLCB TBM
Creators
- 1. Institute for Plasma Research, Bhat, Gandhinagar 382428, Gujarat (India)
- 2. Centre of Plasma Physics – Institute for Plasma Research, Tepesia, Sonapur, Guwahati 782402, Assam (India)
- 3. ATD Section, Bhabha Atomic Research Centre, Mumbai 400085 (India)
Description
Highlights: ► A 3D numerical approach is applied to capture the thermo-fluid MHD flow modification at higher Hartmann number in a single channel of LLCB TBM. ► The heat transfer has been studied by keeping hot breeders at both sides of single rectangular flow channel. ► The results suggest modification in steady state velocity profile as the liquid flows along the flow length. ► The temperature in various zone is found to remain well within the allowable limit. ► The buoyancy effect on the MHD pressure drop has also been studied by considering the variation of density with temperature. - Abstract: India is developing lead lithium cooled ceramic breeder (LLCB) blanket for its DEMO fusion reactor. The mock-up blanket (TBM), using this concept, will be tested in ITER for its tritium breeding and high-grade heat extraction efficiency. In this TBM, pressurized helium is used to remove the heat from first wall, top and bottom plates of TBM. The Pb–Li is used to extract heat from the breeder zones. The flow of Pb–Li with average velocity 0.1 m/s inside the channel can be significantly modified due to MHD effects, which arise because of the presence of strong toroidal magnetic field. A numerical approach is established to capture this flow modification at higher Hartmann numbers (≥20,000). As a validation part of the developed code, MHD phenomenon is studied in 2-D square geometry and numerically obtained velocity profile is compared with available Hunt's analytical results. Thermo-fluid MHD analysis using this code, has been carried out for single rectangular duct of LLCB TBM. The heat transfer has been studied by keeping hot breeders at both sides of the flow channel. The results suggest modification in steady state MHD velocity profile as the liquid flows along the flow length. However, the temperature in various zone remains well within the maximum allowable limit.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2012.01.010Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2012.01.010;
- PII
- S0920-3796(12)00012-9;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 87
- Journal Issue
- 5-6
- Journal Page Range
- p. 498-502
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 10. international symposium on fusion nuclear technology
- Acronym
- ISFNT-10
- Dates
- 11-16 Sep 2011
- Place
- Portland, OR (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 44037023
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDING; BREEDING BLANKETS; COMPUTERIZED SIMULATION; FIRST WALL; FLOW RATE; HARTMANN NUMBER; HEAT EXTRACTION; HEAT TRANSFER; HELIUM; ITER TOKAMAK; LEAD; LIQUID FLOW; LITHIUM; MAGNETIC FIELDS; MAGNETOHYDRODYNAMICS; PRESSURE DROP; STEADY-STATE CONDITIONS; TEMPERATURE DEPENDENCE; THREE-DIMENSIONAL CALCULATIONS; TRITIUM
- Descriptors DEC
- ALKALI METALS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CLOSED PLASMA DEVICES; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY TRANSFER; FLUID FLOW; FLUID MECHANICS; FLUIDS; GASES; HYDRODYNAMICS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MECHANICS; METALS; NONMETALS; NUCLEAR FUEL CONVERSION; NUCLEI; ODD-EVEN NUCLEI; RADIOISOTOPES; RARE GASES; REACTOR COMPONENTS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2012 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.