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...

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Detalles Bibliográficos
Autores principales: Sergey Ananyev, Andrei Kukushkin
Formato: Artículo
Lenguaje:English
Publicado: MDPI AG 2023-07-01
Colección:Applied Sciences
Materias:
Acceso en línea:https://www.mdpi.com/2076-3417/13/14/8552