Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, ASTAR 811C, and ASTAR 1211C after 5000 hours in flowing lithium at 1370 C (2500 F) are presented. No gross corrosion effects were observed. However, hafnium and nitrogen transfer to cooler regions within the loop were noted. Oxygen was in general removed from test specimens, but there was no evidence to indicate that it was a major factor in the mass transfer process. Carbon and hydrogen transfer were not detected
Liquid lithium is a leading candidate as a tritium breeding material for fusion reactors because of ...
The effect of long-term, elevated-temperature vacuum and lithium exposures on the mechanical propert...
Two thermal convection loops (TCLs) fabricated from annealed alloy 718 continuously circulated mercu...
A T-111 alloy (Ta-8% W-2% Hf) forced-convection loop containing molten lithium was operated 3000 hr ...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
Simulated nuclear fuel element specimens, consisting of uranium mononitride (UN) fuel cylinders clad...
The liquid ammonia and vacuum distillation techniques were found to be satisfactory for removing lit...
Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 7).Mode of acc...
The corrosion of types 304L and 316 austenitic stainless steel by flowing lithium was studied in the...
Plots are presented which show the distribution of oxygen between liquid lithium and tantalum or nio...
Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 5...
In spatially nonisothermal flowing liquid metal systems, selected constitutents of the containment m...
Instrumentation and performance of Rankine cycle corrosion test loop with alkali meta
Operational characteristics of two loop lithium boiling potassium system of niobium zirconium Rankin...
Liquid lithium is a leading candidate as a tritium breeding material for fusion reactors because of ...
The effect of long-term, elevated-temperature vacuum and lithium exposures on the mechanical propert...
Two thermal convection loops (TCLs) fabricated from annealed alloy 718 continuously circulated mercu...
A T-111 alloy (Ta-8% W-2% Hf) forced-convection loop containing molten lithium was operated 3000 hr ...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
Simulated nuclear fuel element specimens, consisting of uranium mononitride (UN) fuel cylinders clad...
The liquid ammonia and vacuum distillation techniques were found to be satisfactory for removing lit...
Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 7).Mode of acc...
The corrosion of types 304L and 316 austenitic stainless steel by flowing lithium was studied in the...
Plots are presented which show the distribution of oxygen between liquid lithium and tantalum or nio...
Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 5...
In spatially nonisothermal flowing liquid metal systems, selected constitutents of the containment m...
Instrumentation and performance of Rankine cycle corrosion test loop with alkali meta
Operational characteristics of two loop lithium boiling potassium system of niobium zirconium Rankin...
Liquid lithium is a leading candidate as a tritium breeding material for fusion reactors because of ...
The effect of long-term, elevated-temperature vacuum and lithium exposures on the mechanical propert...
Two thermal convection loops (TCLs) fabricated from annealed alloy 718 continuously circulated mercu...