Fatigue Crack Propagation In Fast Neutron Irradiated Stainless Steels And Welds
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Author | : P. Shahinian |
Publisher | : |
Total Pages | : 14 |
Release | : 1975 |
Genre | : Crack propagation |
ISBN | : |
Neutron irradiation to a fluence of 1.2 x 1022 neutrons (n)/cm2, > 0.1 MeV caused a small decrease in the resistance to fatigue crack propagation of Types 308 and 316 submerged-arc weld metals at 800 and 1100°F (427 and 593°C). Nevertheless, the postirradiation fatigue resistances of the weld metals were generally comparable to those of the corresponding base metal. Fatigue crack growth in Types 304 and 316 base metals were also affected by irradiation; the effect was dependent on the stress intensity factor and temperature. Although resistance to crack growth of cold-worked (25 percent) Type 304 stainless steel was only slightly reduced at 800°F by irradiation, the resistance at 1100°F was reduced markedly.
Author | : |
Publisher | : |
Total Pages | : 20 |
Release | : 1980 |
Genre | : |
ISBN | : |
The fatigue and creep-fatigue crack propagation performance of Type 316 stainless steel was investigated following fast neutron irradiation to a fluence level of about 5 x 10 to the 22nd power n/sq. cm (> O.1 MeV), about 26 displacements per atom (dpa), at 649 C. The results from fatigue tests of both annealed and 20 percent cold worked steel show that irradiation produced no significant effect on crack propagation rate when compared with unirradiated steel tested at 649 C. For tests conducted using creep-fatigue cycling, the inclusion of a two-minute hold time at the maximum cyclic load resulted in a marked increase in the crack propagation rate of the annealed steel. The effect of a one-minute hold time in the 20-percent cold worked, irradiated steel was to significantly increase the crack propagation rate at 649 C. Scanning electron microscope examination of the tested specimens revealed that the crack propagation mode of the specimens which exhibited increased crack propagation rates was primarily intergranular while a transgranular mode was observed for specimens with lower crack propagation rates. The results point toward a synergistic relationship between thermochemical history, precipitate formation, and hold time effects as the responsible mechanism for the crack propagation performance. (Author).
Author | : C. J. Baroch |
Publisher | : ASTM International |
Total Pages | : 625 |
Release | : 1975 |
Genre | : |
ISBN | : |
Author | : P. Shahinian |
Publisher | : |
Total Pages | : 16 |
Release | : 1973 |
Genre | : Compressible flow |
ISBN | : |
Resistance to fatigue crack propagation of pre- and postirradiation AISI Types 304 and 316 stainless steels was determined at 800 and 1100 F (427 and 593 C) using the fracture mechanics approach. The effect of irradiation on fatigue resistance was dependent upon test temperature and irradiation conditions. In general, irradiation degraded fatigue resistance at 1100 F (593 C) but at 800 F (427 C) enhancement as well was observed. In both steels irradiated in a thermal reactor to a fluence of 1.8 x 1021 n/cm2 >0.1 MeV, fatigue crack growth rates at 800 F (427 C) were lower than in the unirradiated steels for a given stress intensity factor range (?K). However, at 1100 F (593 C) the effect was reversed and crack growth rates were higher in the irradiated steels. Irradiation in a fast reactor to a fluence of ~1.2 x 1022 n/cm2 >0.1 MeV caused fatigue crack growth rates at 800 F (427 C) to increase at low values of ?K and decrease at high values of ?K. At 1100 F (593 C) the crack growth rates in the irradiated steel were either the same as or higher than in the unirradiated steel. The influence of irradiation on fatigue life generally reflected the effect observed on crack growth rate.
Author | : J. Gravenor |
Publisher | : |
Total Pages | : 0 |
Release | : 1981 |
Genre | : |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 0 |
Release | : 1981 |
Genre | : |
ISBN | : |
The failure modes and dislocation substructure produced by fatigue crack propagation at 593 C in fast neutron irradiated and unirradiated Type 316 stainless steel were studied. The results indicate that the dislocation substrate produced by the crack propagation during both cyclic and combined cyclic-static loading conditions was directly dependent on the extent of matrix deformation as reflected by the mode of crack propagation. The results are consistent with the activation of either grain boundary or matrix mechanisms for deformation, as related to loading conditions, at the temperature investigated. The influence of neutron irradiation was to alter the operation of the basic deformation mechanisms by the increased difficulty of matrix dislocation motion resulting from the irradiation-induced defect production. (Author).
Author | : |
Publisher | : |
Total Pages | : 152 |
Release | : 1977-11 |
Genre | : Nuclear engineering |
ISBN | : |
Author | : United States. Energy Research and Development Administration |
Publisher | : |
Total Pages | : 818 |
Release | : 1977 |
Genre | : Medicine |
ISBN | : |
Author | : United States. Energy Research and Development Administration. Technical Information Center |
Publisher | : |
Total Pages | : 1118 |
Release | : 1976 |
Genre | : Force and energy |
ISBN | : |
Author | : |
Publisher | : |
Total Pages | : 724 |
Release | : 1976 |
Genre | : Nuclear energy |
ISBN | : |