A new concept for an advanced fusion first wall and blanket has been identified. The key feature of the concept is the use of the heat of vaporization of lithium (about 10 times higher than water) as the primary means for capturing and removing the fusion power. A reasonable range of boiling temperatures of this alkali metal is 1200 to 1400 C, corresponding with a saturation pressure of 0.035 to 0.2 MPa. Calculations indicate that a evaporative system with Li at {approximately}1200 C can remove a first wall surface heat flux of >2 MW/m2 with an accompanying neutron wall load of >10 MW/m2. Work to date shows that the system provides adequate tritium breeding and shielding, very high thermal conversion efficiency, and low system pressur...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
A new concept for an advanced fusion first wall and blanket has been identified. The key feature of ...
The attractive features and scientific challenges offered by the liquid wall systems render them str...
The many possible combinations of blanket materials, tritium generation and recovery systems, and po...
Liquids ({approximately}7 neutron mean free paths thick) with certain restrictions can probably be u...
The lithium waterfall reactor is described as a concept in which liquid lithium serves as the coolan...
The water-cooled lithium lead breeding blanket is one of the candidate systems considered for the im...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
A self-cooled lithium-vanadium blanket concept capable of operating with 2 MW/m2 surface heat flux a...
At present, the only solid material believed to be a viable option for plasma-facing components (PFC...
The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by t...
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
A new concept for an advanced fusion first wall and blanket has been identified. The key feature of ...
The attractive features and scientific challenges offered by the liquid wall systems render them str...
The many possible combinations of blanket materials, tritium generation and recovery systems, and po...
Liquids ({approximately}7 neutron mean free paths thick) with certain restrictions can probably be u...
The lithium waterfall reactor is described as a concept in which liquid lithium serves as the coolan...
The water-cooled lithium lead breeding blanket is one of the candidate systems considered for the im...
An aggressive low aspect ratio scoping fusion reactor design indicated that a 2 GW(e) reactor can ha...
The feasibility of fusion reactor blankets with low residual activity is examined. Several designs a...
A self-cooled lithium-vanadium blanket concept capable of operating with 2 MW/m2 surface heat flux a...
At present, the only solid material believed to be a viable option for plasma-facing components (PFC...
The efficiencies of blankets for fusion reactors are usually in the range of 30 to 40%, limited by t...
The water-cooled lithium-lead (PbLi) breeding blanket is one of the candidate systems considered for...
Developing a reactor compatible divertor has been identified as a particularly challenging technolog...
The water-cooled lithium–lead breeding blanket is a candidate option for the European Demonstration ...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...