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Evaluation of laser welding techniques for hydrogen transmission. Final report, September 1977-November 1979

Description: This program was established to determine the feasibility of laser beam welding as a fabrication method for hydrogen transmission and is a precursor in the effort to systematically provide the technological base necessary for large-scale, economic pipeline transmission of fuel for a hydrogen energy system. The study contributes to the technology base by establishing the effect of conventional weld processes and laser beam welding on the mechanical properties of two classes of steels in an air a… more
Date: May 1, 1980
Creator: Mucci, J
Partner: UNT Libraries Government Documents Department
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GCFR core cladding temperature limits

Description: This paper reviews the phenomena that affect selection of the GCFR cladding faulted temperature limit. The limiting effects are determined to be clad melting, strength and oxidation rate. The selected temperature limit is 1300/sup 0/C (2370/sup 0/F). The limits for normal, upset and emergency events are also breifly reviewed, and some changes under consideration are discussed.
Date: May 1, 1980
Creator: Day, J.M. & LaBar, M.P.
Partner: UNT Libraries Government Documents Department
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Corrosion of high Ni-Cr alloys and Type 304L stainless steel in HNO/sub 3/-HF

Description: Nineteen alloys were evaluated as possible materials of construction for steam heating coils, the dissolver vessel, and the off-gas system of proposed facilities to process thorium and uranium fuels. Commercially available alloys were found that are satisfactory for all applications. With thorium fuel, which requires HNO/sub 3/-HF for dissolution, the best alloy for service at 130/sup 0/C when complexing agents for fluoride are used is Inconel 690; with no complexing agents at 130/sup 0/C, Inco… more
Date: April 1, 1980
Creator: Ondrejcin, R.S. & McLaughlin, B.D.
Partner: UNT Libraries Government Documents Department
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Attack of high-strength, oxidation-resistant alloys during in-can melting of simulated waste glasses

Description: The restistance of candidate canister alloys to penetration under the most severe conditions expected during in-can melting was directly proportional to the chromium content of the alloy, and inversely proportional to the Na/sub 2/O content of the glass melt. Specimens were exposed for 24 hours, which is the time required for in-can melting full-size waste-glass forms based on tests carried out at Pacific Northwest Laboratories (PNL) and at SRL. The penetration resistance to Frit 211 at 1150/su… more
Date: January 1, 1980
Creator: Rankin, W.N.
Partner: UNT Libraries Government Documents Department
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Corrosion in lithium-stainless steel thermal-convection systems

Description: The corrosion of types 304L and 316 austenitic stainless steel by flowing lithium was studied in thermal-convection loops operated at 500 to 650/sup 0/C. Both weight and compositional changes were measured on specimens distributed throughout each loop and were combined with metallographic examinations to evaluate the corrosion processes. The corrosion rate and mass transfer characteristics did not significantly differ between the two austenitic stainless steels. Addition of 500 or 1700 wt ppM N… more
Date: January 1, 1980
Creator: Tortorelli, P. F.; DeVan, J. H. & Selle, J. E.
Partner: UNT Libraries Government Documents Department
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Ferrous alloy metallurgy - liquid lithium corrosion and welding. Progress report, January 1-December 31, 1980

Description: Fatigue crack growth has been used to evaluate the interaction between liquid lithium and an imposed stress. Fatigue crack growth data on type 304L stainless steel at 700C and 2 1/4Cr-1Mo steel between 500 and 700C show that for all imposed test conditions (i.e. frequency, temperature, and nitrogen content in the lithium) the interaction of lithium with the strain at the crack tip results in enhanced crack growth rates. The enhanced growth rates result from the effects of either enhanced grain … more
Date: 1980~
Creator: Olson, D. L. & Matlock, D. K.
Partner: UNT Libraries Government Documents Department
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Fractography of hydrogen-embrittled iron-chromium-nickel alloys

Description: Tensile specimens of iron-chromium-nickel base alloys were broken in either a hydrogen environment or in air following thermal charging with hydrogen. Fracture surfaces were examined by scanning electron microscopy. Fracture morphology of hydrogen-embrittled specimens was characterized by: changed dimple size, twin-boundary parting, transgranular cleavage, and intergranular separation. The nature and extent of the fracture mode changes induced by hydrogen varied systematically with alloy compos… more
Date: January 1, 1980
Creator: Caskey, G. R., Jr.
Partner: UNT Libraries Government Documents Department
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Hydrogen assisted fracture of sensitized Type 304L austenitic stainless steel

Description: Sensitized specimens of Type 304L stainless steel were tensile tested in atmospheres of hydrogen and helium at high pressure, and in air at ambient pressure. Comparison tensile tests were made with solution-annealed specimens of Type 304L stainless steel in the same atmosphere. When both specimens were tested in high-pressure hydrogen, the sensitized specimens had greater loss in ductility and increased tendency to intergranular fracture. For the sensitized specimens, plastic strain to failure … more
Date: January 1, 1980
Creator: Caskey, G. R., Jr.
Partner: UNT Libraries Government Documents Department
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J-controlled crack growth as an indicator of hydrogen-stainless steel compatibility

Description: The J-integral was evaluated as a parameter to characterize fracture of stainless steels and as a measure of hydrogen damage. C-shaped specimens of type 304L, 316, and 21-6-9 stainless steels were tested in high pressure helium and hydrogen. The critical force for crack initiation (Jm), and tearing resistance (dJ/da) were decreased by hydrogen in all three alloys. The J-integral appears useful as a measure of hydrogen compatibility because it is sensitive to both test environment and microstruc… more
Date: January 1, 1980
Creator: Dietrich, M. R.; Caskey, G. R., Jr. & Donovan, J. A.
Partner: UNT Libraries Government Documents Department
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Response to annealing and reirradiation of AISI 304L stainless steel following initial high-dose neutron irradiation in EBR-II. [LMFBR]

Description: The object of this study was to measure the stability of irradiation-induced microstructure upon annealing and, by selectively annealing out some of these features and reirradiating the material, it was expected that information could be gained concerning the role of microstructural changes in the void swelling process. Transmission electron microscopic examinations of isochronally annealed (200 to 1050/sup 0/C) AISI 304L stainless steel, which had been irradiated at approximately 415/sup 0/C t… more
Date: January 1, 1980
Creator: Porter, D. L.; McVay, G. L. & Walters, L. C.
Partner: UNT Libraries Government Documents Department
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