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...

Disgrifiad llawn

Manylion Llyfryddiaeth
Prif Awduron: Sergey Ananyev, Andrei Kukushkin
Fformat: Erthygl
Iaith:English
Cyhoeddwyd: MDPI AG 2023-07-01
Cyfres:Applied Sciences
Pynciau:
Mynediad Ar-lein:https://www.mdpi.com/2076-3417/13/14/8552