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...
Những tác giả chính: | , |
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Định dạng: | Bài viết |
Ngôn ngữ: | English |
Được phát hành: |
MDPI AG
2023-07-01
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Loạt: | Applied Sciences |
Những chủ đề: | |
Truy cập trực tuyến: | https://www.mdpi.com/2076-3417/13/14/8552 |