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Fusion energy: Progress, partnerships, and the path to deployment
Over the past decade, fusion energy has moved decisively from scientific aspiration toward a credible pathway to a new energy technology. Thanks to long-term federal support, we have significantly advanced our fundamental understanding of plasma physics—the behavior of the superheated gases at the heart of fusion devices. This knowledge will enable the creation and control of fusion fuel under conditions required for future power plants. Our progress is exemplified by breakthroughs at the National Ignition Facility and the Joint European Torus.
Y. Iwai, Y. Misaki, T. Hayashi, T. Yamanishi, S. Konishi, M. Nishi, R. Ninomiya, S. Yanagimachi, S. Senrui, H. Yoshida
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1126-1130
Isotope Separation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22759
Articles are hosted by Taylor and Francis Online.
The water detritiation system (WDS) of tritium plant for the International Thermonuclear Experimental Reactor (ITER) was designed. The concept of the Combined Electrolysis Catalytic Exchange (CECE) process was selected for the WDS. The design conditions are (a) tritium concentration of waste water: 3.7 × 1010∼3.7 × 1011 Bq/kg, (b) waste water flow rate: 20 kg/h (1100 mol/h), a net working rate: 300 days, annual capacity: 150 tons/year (c) tritium concentration in the H2 discharged to environment: 6.5 x 101 Bq/m3, (d) tritium concentration in the H2O vapor discharged to environment: 3.7 x 103 Bq/m3, (e) tritium concentration in the electrolyzer: ∼ 1.85 × 1013 Bq/kg. Tritium concentration in the electrolyzer is determined considering the lifetime of the electrolyzer which depends on tritium concentration. Design value of height of a unit (30cm) of water-hydrogen isotopic exchange column and the correlation between the column internal flow rates and the column diameter were determined based on similar system for Japanese advanced thermal reactor (Fugen) moderated with heavy water.
