Calculation of Consistent Plasma Parameters for DEMO-FNS Using Ionic Transport Equations and Simulation of the Tritium Fuel Cycle

Calculation of Consistent Plasma Parameters for DEMO-FNS Using Ionic Transport Equations and Simulation of the Tritium Fuel Cycle

Modeling the D and T fluxes in Fusion Neutron Source based on a tokamak fuel cycle systems was performed consistently with the core and divertor plasma. An indirect integration of ASTRA, SOLPS4.3, and FC-FNS codes is used. The feedback coupling is realized between the pumping and puffing systems in...

पूर्ण विवरण

ग्रंथसूची विवरण
मुख्य लेखकों:	Sergey Ananyev, Andrei Kukushkin
स्वरूप:	लेख
भाषा:	English
प्रकाशित:	MDPI AG 2023-07-01
श्रृंखला:	Applied Sciences
विषय:	fusion neutron source tokamak hydrogen isotopes D-T fuel cycle integrated plasma simulations ion transport equations
ऑनलाइन पहुंच:	https://www.mdpi.com/2076-3417/13/14/8552

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Correction: Ananyev et al. Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source. <i>Appl. Sci.</i> 2021, <i>11</i>, 7565
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