Call Number (LC) Title Results
E 1.99:conf-740341--1 Design progress on the LMFBR demonstration plant. Subject No. 20 1
E 1.99:conf-740346--1 Distribution of plutonium in a rock containment environment 1
E 1.99: conf-740346--2 Fixation of radioactive waste by hydrothermal reactions with clays 1
E 1.99:conf-740401--1 End to hypothetical safety 1
E 1.99: conf-740401--3 Recriticality considerations in LMFBR accidents 1
E 1.99: conf-740401--5 Sodium fire protection by space isolation with inert gas flooding 1
E 1.99:conf-740401--11 Safety related criteria and design features in the Clinch River Breeder Reactor Plant 1
E 1.99:conf-740401--13 Effect of partial blockages in simulated LMFBR fuel assemblies 1
E 1.99:conf-740401--p1 Proceedings of the fast reactor safety meeting, Beverly Hills, California, April 2--4, 1974
Summary of autoclave TREAT tests on molten-fuel--coolant interactions
R-series loss-of-flow safety experiment in TREAT
Fuel vaporization and quenching by cold sodium interpretation of TREAT Test S-11.
Review of TREAT experiments in support of Transient Overpower (TOP) analysis for fast reactor safety 		5
E 1.99:conf-740401--p2 Improvements in modeling fuel--coolant interactions and interpretation of the S-11 TREAT test
Proceedings of the fast reactor safety meeting, Beverly Hills, California, April 2--4, 1974 		2
E 1.99:conf-740401--p3 Current status and experimental basis of the SAS LMFBR accident analysis code system
Proceedings of the fast reactor safety meeting, Beverly Hills, California, April 2--4, 1974
Estimate of LMFBR steam generator system reliability and availability 		3
E 1.99: conf-740402--1 Direct conversion of neutron energy and other advantages of a large yield per pulse, inertial-confinement fusion reactor 1
E 1.99:conf-740402--2 Transport calculations for D-T burning Tokamak reactors 1
E 1.99:conf-740402--3 Cross-section sensitivity of tritium breeding in fusion reactor blankets 1
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