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...
Main Authors: | Sergey Ananyev, Andrei Kukushkin |
---|---|
Format: | Article |
Language: | English |
Published: |
MDPI AG
2023-07-01
|
Series: | Applied Sciences |
Subjects: | |
Online Access: | https://www.mdpi.com/2076-3417/13/14/8552 |
Similar Items
-
Selection of Fuel Isotope Composition in Heating Injectors of the FNS-ST Compact Fusion Neutron Source
by: Sergey Ananyev, et al.
Published: (2021-08-01) -
Neutronics Simulations for DEMO Diagnostics
by: Raul Luís, et al.
Published: (2023-05-01) -
Impurity study in the dimensionless and dimensional isotope identity experiment between JET Deuterium and Tritium L-mode plasmas
by: A. Chomiczewska, et al.
Published: (2024-01-01) -
Performance comparison between the ITER- and DEMO-like plasmas using CRONOS simulations
by: Boonyarit Chatthong, et al.
Published: (2019-10-01) -
Conceptual design of DEMO blanket materials test modules for A-FNS
by: Saerom Kwon, et al.
Published: (2020-12-01)