A key feasibility issue for the ITER Vanadium/Lithium breeding blanket is the question of insulator coatings. Design calculations show that an electrically insulating layer is necessary to maintain an acceptably low MHD pressure drop. To begin experimental investigations of the MHD performance of candidate insulator materials and the technology for putting them in place, a new test section was prepared. Aluminum oxide was chosen as the first candidate insulating material because it may be used in combination with NaK in the ITER vacuum vessel and/or the divertor. Details on the methods used to produce the aluminum oxide layer as well as the microstructures of the coating and the aluminide sublayer are presented and discussed. The overall MH...
ITER is incorporating two types of In-Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Mode...
The design of breeding blankets represents the major challenge for fusion reactor engineering becaus...
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of ...
A key feasibility issue for the ITER Vanadium/Lithium breeding blanket is the question of insulator ...
The Vanadium/Lithium system has been the recent focus of ANL`s Blanket Technology Pro-ram, and for t...
The self-cooled lithium/vanadium blanket concept has several attractive features for fusion power sy...
To test the magnetohydrodynamic (MHD) pressure drop reduction performance of candidate insulator coa...
The self-cooled lithium blanket concept with a vanadium structure offers a potential for high perfor...
The blanket system is one of the most important components in a fusion reactor because it has a majo...
The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the ef...
The objective of this task is to develop the required data base and demonstrate the performance of a...
The liquid-metal blanket concept for fusion reactors requires an coating on the first-wall structura...
According to the most recently revised European design strategy for DEMO breeding blankets, mature c...
According to the most recently revised European design strategy for DEMO breeding blankets, mature c...
This paper provides a description of the most promising liquid breeder blankets currently proposed f...
ITER is incorporating two types of In-Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Mode...
The design of breeding blankets represents the major challenge for fusion reactor engineering becaus...
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of ...
A key feasibility issue for the ITER Vanadium/Lithium breeding blanket is the question of insulator ...
The Vanadium/Lithium system has been the recent focus of ANL`s Blanket Technology Pro-ram, and for t...
The self-cooled lithium/vanadium blanket concept has several attractive features for fusion power sy...
To test the magnetohydrodynamic (MHD) pressure drop reduction performance of candidate insulator coa...
The self-cooled lithium blanket concept with a vanadium structure offers a potential for high perfor...
The blanket system is one of the most important components in a fusion reactor because it has a majo...
The ITER project is considering the inclusion of two sets of in-vessel coils, one to mitigate the ef...
The objective of this task is to develop the required data base and demonstrate the performance of a...
The liquid-metal blanket concept for fusion reactors requires an coating on the first-wall structura...
According to the most recently revised European design strategy for DEMO breeding blankets, mature c...
According to the most recently revised European design strategy for DEMO breeding blankets, mature c...
This paper provides a description of the most promising liquid breeder blankets currently proposed f...
ITER is incorporating two types of In-Vessel Coils (IVCs): ELM Coils to mitigate Edge Localized Mode...
The design of breeding blankets represents the major challenge for fusion reactor engineering becaus...
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of ...