Simulated nuclear fuel element specimens, consisting of uranium mononitride (UN) fuel cylinders clad with tungsten-lined T-111, were exposed for up to 7500 hr at 1040 C (1900 F) in a pumped-lithium loop. The lithium flow velocity was 1.5 m/sec (5 ft/sec) in the specimen test section. No evidence of any compatibility problems between the specimens and the flowing lithium was found based on appearance, weight change, chemistry, and metallography. Direct exposure of the UN to the lithium through a simulated cladding crack resulted in some erosion of the UN in the area of the defect. The T-111 cladding was ductile after lithium exposure, but it was sensitive to hydrogen embrittlement during post-test handling
Cerment materials (HfC - 10 wt% W; HfC - 10 wt% TaC - 10 wt%W; HfC - 2 wt% CbC - 8 wt% Mo;Hfn - 10 w...
Lithium corrosion of niobium zirconium alloys and yttrium oxides at high flow velocitie
An exploratory out-of-reactor investigation was made of the effects of short-time temperature excurs...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
Two groups of six fuel pins each were assembled, encapsulated, and irradiated in the Plum Brook Reac...
The effect of long-term, elevated-temperature vacuum and lithium exposures on the mechanical propert...
Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 5...
The design and successful operation of three tantalum alloy (Ta-8W-2Hf) clad uranium mononitride (UN...
Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 15-16).Mode of...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
The liquid ammonia and vacuum distillation techniques were found to be satisfactory for removing lit...
The effect of controlled nitrogen additions was evaluated on the mechanical properties of T-111 (Ta-...
Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, AS...
Fuel volume swelling and clad diametral creep strains were calculated for five fuel pins, clad with ...
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in ...
Cerment materials (HfC - 10 wt% W; HfC - 10 wt% TaC - 10 wt%W; HfC - 2 wt% CbC - 8 wt% Mo;Hfn - 10 w...
Lithium corrosion of niobium zirconium alloys and yttrium oxides at high flow velocitie
An exploratory out-of-reactor investigation was made of the effects of short-time temperature excurs...
Metallographic and ductility effects of lithium on tungsten-lined titanium alloy clad uranium mononi...
Two groups of six fuel pins each were assembled, encapsulated, and irradiated in the Plum Brook Reac...
The effect of long-term, elevated-temperature vacuum and lithium exposures on the mechanical propert...
Materials for a lithium-cooled space power reactor concept must be chemically compatible for up to 5...
The design and successful operation of three tantalum alloy (Ta-8W-2Hf) clad uranium mononitride (UN...
Prepared at Lewis Research Center.Cover title.Includes bibliographical references (p. 15-16).Mode of...
The effects were studied of low-pressure air on contamination and corrosion in the tantalum alloy T-...
The liquid ammonia and vacuum distillation techniques were found to be satisfactory for removing lit...
The effect of controlled nitrogen additions was evaluated on the mechanical properties of T-111 (Ta-...
Experimental results from a test to evaluate interstitial element mass transfer effects on T-111, AS...
Fuel volume swelling and clad diametral creep strains were calculated for five fuel pins, clad with ...
Production engineering and compatibility tests of Ta-8W-2Hf clad UN nuclear fuel element for use in ...
Cerment materials (HfC - 10 wt% W; HfC - 10 wt% TaC - 10 wt%W; HfC - 2 wt% CbC - 8 wt% Mo;Hfn - 10 w...
Lithium corrosion of niobium zirconium alloys and yttrium oxides at high flow velocitie
An exploratory out-of-reactor investigation was made of the effects of short-time temperature excurs...