|
E 1.99: conf-760935-24
|
Operating point considerations for the Reference Theta-Pinch Reactor (RTPR) |
1 |
|
E 1.99:conf-760935-25
|
Factors affecting calculations of dose resulting from a tritium release into the atmosphere |
1 |
|
E 1.99: conf-760935-26
|
Neutronic data consistency analysis for lithium blanket and shield design |
1 |
|
E 1.99:conf-760935-27
|
Current CTR-related tritium handling studies at ORNL |
1 |
|
E 1.99: conf-760935-28
|
Helium generation and diffusion in graphite and some carbides. [14. 9 and 14. 4 MeV neutrons] |
1 |
|
E 1.99: conf-760935-29
|
Environmental control of the tritium inventory in a fusion reactor facility |
1 |
|
E 1.99: conf-760935-30
|
Rotating target neutron source II progress report. |
1 |
|
E 1.99:conf-760935-31
|
PLT and TFTR neutral beam systems |
1 |
|
E 1.99:conf-760935-32
|
Oak Ridge EPR and TNS studies. [Reference design] |
1 |
|
E 1.99: conf-760935-33
|
Technology problems in theta pinch reactors |
1 |
|
E 1.99: conf-760935-34
|
Fission fragment simulation of fusion neutron radiation effects on bulk mechanical properties |
1 |
|
E 1.99: conf-760935-36
|
Status of tokamak plasma physics. [Plasma parameters] |
1 |
|
E 1.99: conf-760935-38
|
Determination of the damage-energy cross section of 14-MeV neutrons from critical-property changes in irradiated Nb₃Sn |
1 |
|
E 1.99: conf-760935-39
|
Scaling for Tormac fusion reactors |
1 |
|
E 1.99: conf-760935-40
|
Neutral-beam design options. [Design and cost optimization] |
1 |
|
E 1.99: conf-760935-41
|
Conceptual design study for a laser fusion hybrid |
1 |
|
E 1.99: conf-760935-44
|
First wall studies of a laser-fusion hybrid reactor design |
1 |
|
E 1.99: conf-760935-45
|
Estimate of thermoelastic heat production from superconducting composites in pulsed poloidal coil systems |
1 |
|
E 1.99:conf-760935-46
|
Plasma driving system for a Tokamak Experimental Power Reactor |
1 |
|
E 1.99:conf-760935-47
|
Tokamak Experimental Power Reactor primary energy conversion system |
1 |
