Model and simulation of a vacuum sieve tray for T extraction from liquid PbLi breeding blankets
Creators
- 1. Ghent University, Department of Materials Science and Engineering, Center of Molecular Modeling, Technologiepark 903, B-9052 Zwijnaarde (Belgium)
- 2. Karlsruhe Institute of Technology, Institute for Technical Physics, Tritium Laboratory Karlsruhe, Hermann-von-Helmholtz Platz 1, D-76344 Eggenstein-Leopoldshafen (Germany)
Description
Highlights: • A simulation tool was developed to analyse, optimise and scale up VST set-ups. • This tool predicts that efficiencies higher than 90% can be reached. • Upscaling to DEMO breeding blanket flow rates results in feasibly sized designs. - Abstract: Tritium self-sufficiency within a nuclear fusion reactor is necessary to demonstrate nuclear fusion as a viable source of energy. Tritium can be produced within liquid eutectic PbLi but then has to be extracted to be refuelled to the plasma. The vacuum sieve tray (VST) method is based on the extraction of tritium from millimetre-scaled oscillating PbLi droplets falling inside a vacuum chamber. A simulation tool was developed describing the fluid dynamics occurring along the PbLi flow and was used to study the influence of the different geometrical and operational parameters on the VST performance. The simulation predicts that extraction efficiencies over 90% can be easily reached according to theory and previous experimental results. The size of the VST extraction unit for a fusion reactor is estimated based on the findings from our single-nozzle model and assuming no T reabsorption. It is found to be in the feasible range. Nevertheless, two approaches are discussed which may further reduce this size by up to 90%. The simulation tool proved to be an easy and powerful way to analyse and optimise VST set-ups at any scale.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2016.05.038Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2016.05.038;
- PII
- S0920-3796(16)30395-7;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 112
- Journal Page Range
- p. 541-547
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48074155
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- BREEDING BLANKETS; COMPUTERIZED SIMULATION; DROPLETS; EUTECTICS; FLOW RATE; FLUID MECHANICS; LEAD; LIQUID METALS; LITHIUM; NOZZLES; PERFORMANCE; PLASMA; THERMONUCLEAR REACTORS; TRITIUM; VACUUM SYSTEMS
- Descriptors DEC
- ALKALI METALS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; ELEMENTS; FLUIDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; LIQUIDS; MECHANICS; METALS; NUCLEI; ODD-EVEN NUCLEI; PARTICLES; RADIOISOTOPES; REACTOR COMPONENTS; SIMULATION; YEARS LIVING RADIOISOTOPES
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.