Results 211 to 220 of about 12,788 (251)

Erosion of 316 stainless steel by dicalcium phosphate

Wear, 1995
Abstract A solids-handling facility for a chemical manufacturing organization was in the planning stage and a concern arose on whether special precautions should be taken to address erosion of stainless steel piping that was intended for use as the conveyance medium.
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Ductility of Irradiated Type 316 Stainless Steel

1973
The effect of fast reactor irradiation on the ductility of annealed AISI Type 316 stainless steel is described in terms of strain rate, temperature, and neutron fluence. Creep and tensile data obtained after EBR-II irradiations are presented and analyzed in terms of controlling deformation mechanisms.
JJ Holmes, AJ Lovell, RL Fish
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Effects of stress on swelling in 316 stainless steel

Journal of Nuclear Materials, 1978
Abstract Stress was found to increase the magnitude of irradiation-induced swelling in 316 stainless steel. Measurement of the densities of pressurized tube specimens, irradiated at temperatures of ~ 430–475°C to peak fluences of ~ 9 × 10 22 n/cm 2 ( E > 0.1 MeV ) in EBR-II, has indicated increased swelling in both the annealed ...
J.F. Bates, E.R. Gilbert
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Electroslag remelting of type 316 stainless steel

JOM, 1973
The Bureau of Mines, in cooperation with the United States Atomic Energy Commission, electroslag remelted two groups of type 316 stainless steel ingots for ultimate conversion to tubing for tests associated with the liquid metal fast-breeder reactor. The reduction in imperfections achieved suggests electroslag remelting as a promising alternative to ...
W. E. Anable, R. H. Nafziger, D. C. Robinson   +2 more
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Helium bubble growth in 316 stainless steel

Radiation Effects, 1983
Abstract A systematic TEM investigation has been made of helium bubble growth in type 316 stainless steel. Commercial stainless steel samples have been vacuum annealed following room temperature helium implantation to a concentration of 5 × 1026 He m−3.
T. R. Armstrong, P. J. Goodhew
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Failure Analysis of 316 Stainless Steel Tubesheet

CONFERENCE 2026
Abstract Austenitic stainless steels (SSs) are used in wide ranging industrial applications, such as heat exchangers, due to their excellent corrosion resistance and high temperature properties. This case study describes the failure analysis performed on a UNS S31603 (316L SS) tubesheet retrieved from the inlet side of a gas cooler ...
Vibha Zaman, Fred Wade, Tyler Scherbarth, SUDHAKAR MAHAJANAM   +3 more
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Irradiation behavior of nanostructured 316 austenitic stainless steel

Journal of Materials Science, 2008
In order to get information about radiation resistance of ultrafine grained austenitic stainless steels, a 316 steel was deformed by high pressure torsion. The mean diameter of the grain after deformation was 40 nm. This material was annealed at 350 °C for 24 h or irradiated with 160 keV iron ions at 350 °C.
Radiguet, Bertrand, Etienne, Auriane, Pareige, Philippe, Sauvage, Xavier, Valiev, R.   +4 more
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Booth dispense with type 316 stainless steel

Anti-Corrosion Manual, 1990
The UK's leading manufacturer of speciality drinks dispensers, Booth Dispensers Ltd of Lytham St. Anne's is now using Sandvik 1802 free cutting stainless steel instead of Type 316 steel for the manufacture of nozzles in its vending equipment.
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Creep of 316 stainless steel under high stresses

Acta Metallurgica, 1978
Abstract The dislocation substructure developed in 316 stainless steel after creep tests at temperatures between 600 and 800°C and stresses between 6 and 38 kg/mm2 has been observed. A gradual transition from equiaxed subgrains at low stresses to a grain orientation dependent duplex substructure at high stresses occurs in the range where ge s
H.-J. Kestenbach, W. Krause, T.L. da Silveira   +2 more
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Wedge crack nucleation in Type 316 stainless steel

Journal of Materials Science, 1977
Type 316 austenitic steel has been heat-treated to produce a range of grain sizes and then creep-tested at 625° C at various stresses so as to examine the nucleation and the factors which effect the nucleation of grain-boundary triple point or “wedge” cracks.
D. G. Morris, D. R. Harries
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