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E 1.99: conf-780508-44
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TRIDENT-CTR a two-dimensional transport code for CTR applications. |
1 |
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E 1.99: conf-780508-45
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Survey of linear magnetic fusion reactors |
1 |
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E 1.99: conf-780508-46
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Small mirror fusion reactors |
1 |
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E 1.99:conf-780508-47
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New impurity control methods for tokamak fusion power reactors |
1 |
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E 1.99:conf-780508-48
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Computations of nuclear response functions with MACK-IV |
1 |
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E 1.99:conf-780508-49
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Equilibrium field coil considerations for tokamak reactors |
1 |
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E 1.99: conf-780508-50
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Maintenance of a multi-cell field reversed mirror reactor |
1 |
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E 1.99: conf-780508-51
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Traps for scavenging hydrogen isotopes |
1 |
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E 1.99: conf-780508-53
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Materials compatibility study of 316 stainless steel at the LLL tritium facility |
1 |
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E 1.99:conf-780508-55
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Evaluation of steam as a potential coolant for nonbreeding blanket designs |
1 |
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E 1.99: conf-780508-56
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Mixing rules for and effects of other hydrogen isotopes and of isotopic swamping on tritium recovery and loss to biosphere from fusion reactors |
1 |
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E 1.99: conf-780508-58
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Effects of waste management on the impact of fusion power |
1 |
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E 1.99:conf-780508-59
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Damage analysis and fundamental studies program. Paper 78-97 |
1 |
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E 1.99: conf-780508-60
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New techniques for inducing plasma current in large tokamak devices |
1 |
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E 1.99: conf-780508-61
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Inertial confinement fusion reactor cavity phenomena |
1 |
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E 1.99: conf-780508-62
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Thorium--uranium cycle ICF hybrid concept |
1 |
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E 1.99: conf-780508-63
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Computer programs for capital cost estimation, lifetime economic performance simulation, and computation of cost indexes for laser fusion and other advanced technology facilities |
1 |
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E 1.99: conf-780508-64
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Energetics of semi-catalyzed-deuterium, light-water-moderated, fusion-fission toroidal reactors |
1 |
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E 1.99: conf-780508-65
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PITR a small-aspect-ratio, small-major-radius ignition test reactor. |
1 |
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E 1.99: conf-780508-66
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Argonne National Laboratory papers presented at third ANS topical meeting on the technology of controlled nuclear fusion |
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