Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 50,000 hr at high temperature. Capsule tests at 1040 C (1900 F) were made of material combinations of prime interest: T-111 in direct contact with uranium mononitride (UN), Un in vacuum separated from T-111 by tungsten wire, UN with various oxygen impurity levels enclosed in tungsten wire lithium-filled T-111 capsules, and TZM and lithium together in T-111 capsules. All combinations were compatible for over 2800 hr except for T-111 in direct contact with UN
Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, AS...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in ...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
Simulated nuclear fuel element specimens, consisting of uranium mononitride (UN) fuel cylinders clad...
Cerment materials (HfC - 10 wt% W; HfC - 10 wt% TaC - 10 wt%W; HfC - 2 wt% CbC - 8 wt% Mo;Hfn - 10 w...
Thermal cycling tests of lithium fluoride compatibility with columbium base alloy
The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C c...
Neutronic design calculations for lithium 7 cooled nuclear reactor for space application
Criticality calculations for small, cylindrical, lithium cooled reactors for space power system
Compatibility tests of molten uranium with tungsten and tungsten-1.5 percent hafniu
Space power system material compatibility tests of selected refractory metal alloys with boiling pot...
The design of bearings for the control system of a fast reactor concept is presented. The bearings a...
The Early Flight Fission - Test Facilities (EFF-TF) team has designed and built an actively pumped l...
Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, AS...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in ...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
Simulated nuclear fuel element specimens, consisting of uranium mononitride (UN) fuel cylinders clad...
Cerment materials (HfC - 10 wt% W; HfC - 10 wt% TaC - 10 wt%W; HfC - 2 wt% CbC - 8 wt% Mo;Hfn - 10 w...
Thermal cycling tests of lithium fluoride compatibility with columbium base alloy
The results of a materials technology program for a long-life (50,000 hr), high-temperature (950 C c...
Neutronic design calculations for lithium 7 cooled nuclear reactor for space application
Criticality calculations for small, cylindrical, lithium cooled reactors for space power system
Compatibility tests of molten uranium with tungsten and tungsten-1.5 percent hafniu
Space power system material compatibility tests of selected refractory metal alloys with boiling pot...
The design of bearings for the control system of a fast reactor concept is presented. The bearings a...
The Early Flight Fission - Test Facilities (EFF-TF) team has designed and built an actively pumped l...
Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, AS...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
The goal of this dissertation is to examine the neutronic properties of a novel type of fusion react...