Data for: Analysis of Promising Technologies of DEMO-FNS Fuel Cycle

Published: 18 August 2020| Version 1 | DOI: 10.17632/67xxtkbghx.1
Contributor:
Sergey Ananyev

Description

The fueling and pumping systems of DEMO-FNS hybrid facility (tokamak-based fusion neutron source with the parameters R/a = 3.2 m/1 m, B = 5 T, Ipl = 4-5 MA, PNBI = 30 MW and РECR = 6 MW) provide plasma feeding by DT-isotopes for maintaining stationary fusion and removal of excess particles from the divertor zones. The fuel cycle systems (FC) architecture design was made based on the hydrogen isotope flows modeling/simulation by the «FC-FNS» model. Since the fuel flows inside the vacuum chamber are distributed over the core and edge plasmas, a coupled modeling of the gas, solid and plasma flows of the fuel mixtures in these areas was performed for the first time. We have chosen a scenario for operation of the NBIs gas supply system and determined the tritium/deuterium ratio in the plasma composition that provides the highest fusion power. In the present work we consider the candidate technologies for hydrogen extraction, isotope separation, detritiation off-gases. Produced a preliminary analysis of the effectiveness of the most promising technologies. The principles of further optimization of the technologies are also under consideration.

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Tritium, Fusion Reactor, Technology

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