|
E 1.99: conf-880417-1
|
A high-fluence fusion neutron source |
1 |
|
E 1.99:conf-880417-2
|
Remote maintenance design activities and research and development accomplishments for the Compact Ignition Tokamak |
1 |
|
E 1.99: conf-880417-4
|
A benchmark-problem specification and calculation using SENSIBL, a one- and two-dimensional sensitivity and uncertainty analysis code of the AARE system |
1 |
|
E 1.99: conf-880417-5
|
Conceptual design of a reversed-field pinch fusion neutron source |
1 |
|
E 1.99: conf-880417-8
|
Beryllium usage in fusion blankets and beryllium data needs. [None] |
1 |
|
E 1.99: conf-880417-9
|
TIBER (Tokamak Ignition/Burn Experimental Reactor) II as a precursor to an international thermonuclear experimental reactor |
1 |
|
E 1.99:conf-880417-10
|
MHD (magnetohydrodynamic) thermal hydraulic analysis of three-dimensional liquid metal flows in fusion blanket ducts |
1 |
|
E 1.99:conf-880417-11
|
Engineering, safety, and economic evaluations of ASPIRE (Advanced Safe Pool Immersed REactor) |
1 |
|
E 1.99:conf-880417-12
|
Lithium corrosion/mass transfer test facility |
1 |
|
E 1.99:conf-880417-13
|
Combined gettering and molten salt process for tritium recovery from lithium |
1 |
|
E 1.99:conf-880417-14
|
Mechanical properties and deformation of polycrystalline lithium orthosilicate |
1 |
|
E 1.99:conf-880417-15
|
Relationship between fabrication parameters and structural characteristics of sintered lithium orthosilicate |
1 |
|
E 1.99:conf-880417-16
|
First wall/blanket/shield design and optimization system |
1 |
|
E 1.99:conf-880417-17
|
The hole of a blanket tritium system on the fusion fuel cycle |
1 |
|
E 1.99:conf-880417-18
|
Design analysis and optimization of self-cooled lithium blankets and shields |
1 |
|
E 1.99:conf-880417-19
|
Blanket technology experiments at Argonne National Laboratory |
1 |
|
E 1.99:conf-880417-20
|
MHD (magnetohydrodynamic) flow tailoring in first wall coolant channels of self-cooled blankets |
1 |
|
E 1.99: conf-880417-21
|
Reactor applications of the compact fusion advanced Rankine (CFAR) cycle for a D-T tokamak fusion reactor |
1 |
|
E 1.99:conf-880417-22
|
Current experimental activities for solid breeder development |
1 |
|
E 1.99: conf-880417-23
|
A turning point in the US Inertial Confinement Fusion Program |
1 |
