2014
DOI: 10.1016/j.fusengdes.2014.04.028
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Tritium management and anti-permeation strategies for three different breeding blanket options foreseen for the European Power Plant Physics and Technology Demonstration reactor study

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Cited by 29 publications
(12 citation statements)
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“…Tritium permeation rate (product of solubility and diffusion coefficient at 1000 • C) to the heat transfer media is evaluated from the experimental data for SiC composite and metals used for heat exchanger and recovery efficiency of tritium from the breeder stream. The tritium concentration of hydrogen fuel which is generated in fusion plant is able to be reduced to approximately 2000 Bq/m 3 if the tritium permeation rate is 10 −15 mol/Pa 1/2 s m and tritium recovery efficiency is 45% which were reported elsewhere [13,14]. As a result, the simulated tritium concentration in each compartment is supposed to be reduced by 40%.…”
Section: Resultsmentioning
confidence: 67%
“…Tritium permeation rate (product of solubility and diffusion coefficient at 1000 • C) to the heat transfer media is evaluated from the experimental data for SiC composite and metals used for heat exchanger and recovery efficiency of tritium from the breeder stream. The tritium concentration of hydrogen fuel which is generated in fusion plant is able to be reduced to approximately 2000 Bq/m 3 if the tritium permeation rate is 10 −15 mol/Pa 1/2 s m and tritium recovery efficiency is 45% which were reported elsewhere [13,14]. As a result, the simulated tritium concentration in each compartment is supposed to be reduced by 40%.…”
Section: Resultsmentioning
confidence: 67%
“…As reported by previous studies [18][19][20], higher TEE contributes to less tritium permeation and less tritium inventory which lead to beneficial effects on coolant purification system (CPS) size and safety issues, along with less tritium extraction system (TES) size.…”
Section: Analysis Modelmentioning
confidence: 81%
“…With the progress of the engineering analysis and the fabrication and test of components with relevant engineering size and features, this method was progressively accepted as reference for the conceptual design of the ITER helium-cooled lithium lead (HCLL) test blanket system (TBS) [8][9][10][11][12]. However, recently published studies suggest that a higher TEE is necessary in view of DEMO relevance and would be beneficial also for ITER operation, and the technical readiness level (TRL) of PbLi TEE remains unsatisfactory [13][14][15]. These studies recommend expedited improvement on this aspect.…”
Section: Introductionmentioning
confidence: 99%
“…• no major operational hazards Thermonuclear fusion expected to be harnessed in the first generation of power plants exhibits promising results regarding all the criteria. Energy production will be based on the following equations 2 1 D + 3 1 T −→ 4 2 He + 1 0 n + 17.6M eV 6 3 Li + 1 0 n −→ 3 1 T + 4 2 He.…”
Section: Introductionmentioning
confidence: 99%