Mass-transport properties to estimate rates of tritium recovery from flibe blanket

Fusion Science and Technology

Volumn 41, Issue 3 II, 2002, Pages 1054-1058

  Fukada, Satoshi ^a   Nishikawa, Masabumi ^a   Sagara, Akio ^a   Terai, Takayuki ^a  

^a KYUSHU UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDING BLANKETS; DIFFUSION; FUSION REACTORS; HEAT TRANSFER; MASS TRANSFER;

COUNTER-CURRENT-EXTRACTION TOWERS;

TRITIUM;

EID: 0036565451     PISSN: 15361055     EISSN: None     Source Type: Journal    
DOI: 10.13182/fst02-a22745     Document Type: Conference Paper

References (22)

1. Blanket comparison and selection study
2. Molten salts in fusion nuclear technology
3. Tritium in molten-salt reactors
4. 2 salt
5. 2 mixture
6. 4 molten salt by permeation through structural materials
7. 4
8. The solubilities of hydrogen fluoride and deuterium fluoride in molten fluorides
9. Conceptual design of a self-cooled Flibe blanket
10. 4
11. Tritium loss in molten Flibe systems
12. Recovery of tritium from liquid blanket of lithium, Li-Pb eutectic alloy or molten salt
13. Calculation of recovery rates of tritium from Flibe blanket
14. Studies on Flibe blanket designs in helical reactor FFHR
15. Physical and chemical aspects of hydrogen transport in fusion reactor materials
16. Effects of mass transfer resistances in fluid and permeable walls on hydrogen permeation in tube-type metal window
17. Hydrogen permeation through duct walls with turbulent-flow
18. 2 eutectic mixture and LiF single salt at elevated temperatures