Modeling And Analysis Of Tritium Transport In Multi Region Lead Lithium Liquid Metal Blankets PDF Download
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Author | : Hongjie Zhang |
Publisher | : |
Total Pages | : 178 |
Release | : 2014 |
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Download Modeling and Analysis of Tritium Transport in Multi-region Lead-lithium Liquid Metal Blankets Book in PDF, ePub and Kindle
It is critical to be able to predict tritium transport in lead-lithium liquid metal (LM) blankets with great accuracy to provide information for fusion reactor safety and economy analyses. However, tritium transport processes are complex and affected by multiple physics such as magnetohydrodynamic (MHD) flow, yet there is no single computer code capable of simulating these phenomena inclusively. Thus the objectives of this research are: 1) to develop mathematical models and computational codes to quantify both tritium distributions throughout the blanket and the permeation loss rate from LM to helium coolant, and 2) to evaluate the key factors that govern tritium permeation and distribution. To accomplish these objectives, a computational framework for analyzing tritium transport phenomena affected by multi-physics and geometric features has been developed. Models have been proposed to integrate multiple tritium transfer processes, including transport inside the LM MHD flow, transfer across the material interface, and permeation through the structural materials and into the helium coolant. Numerical schemes have been developed and implemented in the code to link the different transport mechanisms. The developed model and code have been validated against the data from the US-JA TITAN experiments on hydrogen transport through an [alpha]-Fe/PbLi system and in-reactor tritium release data from lead-lithium, and the modeling results agree well with the experimental data. Parametric studies are performed to quantify the MHD effects, buoyancy effects, PES effects, and the uncertainties of transport properties. The MHD effects reduce the tritium permeation rate due to the higher velocity near the wall. However, the rate of decrease is reduced at higher Hartmann numbers. The buoyancy effect on tritium transport in the LM MHD flows is revealed. Its tritium inventory drops by 80%, and the permeation rate drops by 20% for an upward flow compared to a downward flow. If a PES is introduced on the wall parallel to the magnetic field, tritium loss rate increases by 15% because the velocity is reduced near the front wall. The range of permeation rate change on the basis of uncertainties of transport properties is also provided, and the effect of the uncertainty of tritium solubility is significant. Furthermore, as the FCI electric conductivity increases from 5 to 500 [omega]−1m−1, the tritium permeation rate decreases by 46% due to the increasing velocity in the gap. Lastly, the difference in tritium permeation rates between dual coolant lead lithium (DCLL) and helium-cooled lead lithium (HCLL) blanket concepts is quantified. The tritium permeation loss percentage from the HCLL concept is about one order of magnitude higher than from the DCLL concept (~ 17%. vs. 1.2%). This is mainly due to a much lower velocity and thus a much higher tritium partial pressure for the HCLL concept. The computational models and results stated in this work provide guidance on the lead-lithium liquid metal blanket designs to comply tritium control requirements with regard to the reduction in tritium permeation and inventory and on planning the experiments for database evaluation.
Author | : Luis Angel Sedano Miguel |
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Total Pages | : 200 |
Release | : 1997 |
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Download Understanding and modelling tritium transport phenomena in the lithium-lead water-cooled blanket materials Book in PDF, ePub and Kindle
Author | : Fabrizio Franza |
Publisher | : KIT Scientific Publishing |
Total Pages | : 92 |
Release | : 2013 |
Genre | : |
ISBN | : 3731500124 |
Download Tritium Transport Analysis in HCPB DEMO Blanket with the FUS-TPC Code (KIT Scientific Reports ; 7642) Book in PDF, ePub and Kindle
Author | : |
Publisher | : |
Total Pages | : 24 |
Release | : 1994 |
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Download Comparison of Lithium and the Eutectic Lead Lithium Alloy, Two Candidate Liquid Metal Breeder Materials for Self-cooled Blankets Book in PDF, ePub and Kindle
Liquid metals are attractive candidates for both near-term and long-term fusion applications. The subjects of this comparison are the differences between the two candidate liquid metal breeder materials Li and LiPb for use in breeding blankets in the areas of neutronics, magnetohydrodynamics, tritium control, compatibility with structural materials, heat extraction system, safety, and required R & D program. Both candidates appear to be promising for use in self-cooled breeding blankets which have inherent simplicity with the liquid metal serving as both breeders and coolant. The remaining feasibility question for both breeder materials is the electrical insulation between liquid metal and duct walls. Different ceramic coatings are required for the two breeders, and their crucial issues, namely self-healing of insulator cracks and radiation induced electrical degradation are not yet demonstrated. Each liquid metal breeder has advantages and concerns associated with it, and further development is needed to resolve these concerns.
Author | : |
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Total Pages | : 130 |
Release | : 1978 |
Genre | : Controlled fusion |
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Download Fusion Energy Update Book in PDF, ePub and Kindle
Author | : |
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Total Pages | : |
Release | : 1985 |
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Download Modeling of Tritium Transport in Lithium Aluminate Fusion Solid Breeders Book in PDF, ePub and Kindle
Lithium aluminate is a candidate tritium-breeding material for fusion reactor blankets. One of the concerns with using LiAlO2 is tritium recovery from this material, particularly at low operating temperatures and high fluences. The data from various tritium release experiments with .gamma.-LiAlO2 and related materials are reviewed and analyzed to determine under what conditions bulk diffusion is the rate-limiting mechanism for tritium transport and what the effective bulk diffusion coefficient should be. Steady-state and transient models based on bulk diffusion are developed and used to interpret the data. Design calculations are then performed with the verified models to determine the steady-state inventory and time to reach equilibrium for a full-scale fusion blanket.
Author | : |
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Total Pages | : 294 |
Release | : 1994-10 |
Genre | : Power resources |
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Download Energy Research Abstracts Book in PDF, ePub and Kindle
Author | : Alya Adel Mohamed Badawi |
Publisher | : |
Total Pages | : 302 |
Release | : 1993 |
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Download Modeling and Analysis of Time-dependent Tritium Transport in Lithium-containing Ceramics Book in PDF, ePub and Kindle
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Total Pages | : |
Release | : 1986 |
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Download Modelling of Tritium Transport in a Pin-type Solid Breeder Blanket Book in PDF, ePub and Kindle
This study supplements a larger study of a solid breeder blanket design featuring lithium ceramic pins. This aspect of the study looks at tritium transport, release, and inventory within this blanket design. Li2O and .gamma.-LiAlO2 are the two primary candidates for ceramic solid breeders. .gamma.-LiAlO2 was chosen for this blanket design due to its higher structural stability. Analysis of tritium behavior in solid breeder blankets is of great importance due to its impact on several critical issues: the generation of an adequate amount of fusion fuel, the safety-related issue of keeping radioactive blanket inventories as low as possible, and the release, purge, and economical processing of the bred tritium without undue contamination of the coolant and other reactor structures.
Author | : |
Publisher | : |
Total Pages | : 552 |
Release | : 1985-02 |
Genre | : Power resources |
ISBN | : |
Download Energy Research Abstracts Book in PDF, ePub and Kindle