|
E 1.99: conf-801011-77
|
Westinghouse ICF power plant study |
1 |
|
E 1.99: conf-801011-78
|
Parametric study of a target factory for laser fusion |
1 |
|
E 1.99:conf-801011-79
|
Development of remote welding equipment and techniques for the TFTR vacuum vessel |
1 |
|
E 1.99: conf-801011-81
|
Neutral beam development at LBL/LLNL |
1 |
|
E 1.99: conf-801011-82
|
Design studies of an aluminum first wall for INTOR |
1 |
|
E 1.99: conf-801011-83
|
New concept for a high-repetition-rate reactor for inertial-confinement fusion |
1 |
|
E 1.99: conf-801011-84
|
Reactor systems modeling for ICF hybrids |
1 |
|
E 1.99:conf-801011-85
|
Importance of shield design in minimizing radioactive-material inventory in tokamaks |
1 |
|
E 1.99:conf-801011-86
|
Starfire poloidal coil systems |
1 |
|
E 1.99:conf-801011-87
|
Choice of coolant in commercial tokamak power plants |
1 |
|
E 1.99:conf-801011-88
|
Tritium-handling considerations for ETF and STARFIRE |
1 |
|
E 1.99:conf-801011-89
|
STARFIRE burn cycle |
1 |
|
E 1.99:conf-801011-90
|
Analysis of in-situ tritium recovery from solid fusion-reactor blankets |
1 |
|
E 1.99:conf-801011-92
|
Development of tritium breeding blankets for DT-burning fusion reactors |
1 |
|
E 1.99:conf-801011-93
|
Implications of the DD fuel cycle on tokamak reactor technology considerations |
1 |
|
E 1.99:conf-801011-94
|
Overview of the STARFIRE reference commercial tokamak fusion power reactor design |
1 |
|
E 1.99:conf-801011-95
|
First-wall/blanket materials selection for STARFIRE tokamak reactor |
1 |
|
E 1.99:conf-801011-96
|
Limiter/vacuum system for plasma impurity control and exhaust in tokamaks |
1 |
|
E 1.99:conf-801011-97
|
Lower-hybrid heating and current drive system for the STARFIRE tokamak |
1 |
|
E 1.99:conf-801011-98
|
Neutronic optimization of solid breeder blankets for STARFIRE design |
1 |
