Title :
Analysis on Tritium Permeation and Inventory in China DFLL-TBM for ITER
Author :
Song, Y. ; Huang, Q. ; Wu, Y.
Author_Institution :
Chinese Acad. of Sci., Hefei
Abstract :
The Dual-Functional Lithium-Lead Blanket Module (DFLL-TBM) system is proposed to be tested in ITER. A tritium flow model of the entire DFLL-TBM system was developed, which included the entire TBM and major components of the TBM auxiliary system. And the analysis on tritium permeation and inventory in DFLL-TBM of ITER were done based on the model by using the TAS (Tritium Analysis Software). The following items were taken into consideration, such as the tritium permeation barriers, tritium extraction both from LiPb and helium coolant, helium leakage rate from the cooling system and so on. Some factors, which may probably influence the tritium permeation, were analyzed and evaluated. The results show that the DFLL-TBM is safe from the viewpoint of the tritium according to the ITER TBM safety guard line.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor safety; tritium handling; DFLL-TBM safety; ITER design; LiPb; dual-functional lithium-lead blanket module; helium coolant; tritium permeation; Coolants; Cooling; Equations; Fusion reactor design; Helium; Physics; Production; Safety; System testing; Tokamaks; Liquid metal LiPb; Test Blanket Module; Tritium permeation;
Conference_Titel :
Fusion Engineering, 2007. SOFE 2007. 2007 IEEE 22nd Symposium on
Conference_Location :
Albuquerque, NM
Print_ISBN :
978-1-4244-1193-1
Electronic_ISBN :
978-1-4244-1194-8
DOI :
10.1109/FUSION.2007.4337909