Call Number (LC) Title Results
E 1.99: conf-740402--4 Design study of a neutral injection system for the Fusion Engineering Research Facility (FERF) 1
E 1.99: conf-740402--6 Helium doping of niobium with tritium 1
E 1.99: conf-740402--7 Conceptual design considerations for D-T mirror reactors with and without a fission blanket 1
E 1.99:conf-740402--8 Influence of nonmetallic elements on the compatibility of lithium with fusion reactor materials 1
E 1.99:conf-740402--9 Services to the CTR Community by the Radiation Shielding Information Center 1
E 1.99:conf-740402--10 Tokamak neutral beam heating technology 1
E 1.99:conf-740402--11 Tritium containment and recovery in fusion reactor systems 1
E 1.99: conf-740402--13 Some neutronics aspects of laser-fusion reactors 1
E 1.99: conf-740402--14 Potential lasers for LCTR applications 1
E 1.99: conf-740402--15 Effect of Be(n,2n) multigroup treatment on theta-pinch blanket nucleonics 1
E 1.99: conf-740402--16 Conceptual laser controlled thermonuclear reactor power plant 1
E 1.99: conf-740402--17 Compression-expansion cycles for toroidal fusion reactors 1
E 1.99: conf-740402--18 Comparative analysis of D-T fusion reactor radioactivity and afterheat 1
E 1.99: conf-740402--19 Fusion reactor applications of the high-density linear theta pinch 1
E 1.99: conf-740402--20 Laser fusion power plant systems analysis 1
E 1.99: conf-740402--21 Ergonic optimization and parameter study of the RTPR burn cycle 1
E 1.99:conf-740402--22 Some preliminary considerations of a molten-salt extraction process to remove tritium from liquid lithium fusion reactor blankets 1
E 1.99: conf-740402--23 Review of direct energy conversion of ion beams experimental results and reactor applications. 1
E 1.99: conf-740402--24 Neutrons from a high energy proton beam stop 1
E 1.99:conf-740402--25 Measured and evaluated fast neutron cross sections of nickel and cobalt 1