Download or read book Fatigue Crack Growth and Fracture Toughness Properties of Low Fluence Neutron Irradiated Type 316 and Type 304 Stainless Steels written by MI. De Vries and published by . This book was released on 1987 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Small compact-tension specimens of Type 316 plate and Type 304 forging have been irradiated in the High Flux Reactor (HFR) at Petten, The Netherlands, up to a fluence level of 2 x 1024 neutrons (n) . m-2 (E > 0.1 MeV) at 573 K. Post-irradiation fatigue crack propagation tests and J-integral fracture toughness tests have been performed at the irradiation temperature. Additional tests were made at the higher temperatures of 723 and 823 K.

Download or read book Influence of Radiation on Material Properties written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 806 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures written by P. Shahinian and published by . This book was released on 1973 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.

Download or read book Effects of Radiation on Materials written by D. S. Gelles and published by ASTM International. This book was released on 1996 with total page 1169 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fatigue Life and Crack Growth Predictions of Irradiated Stainless Steels written by Robert William Fuller and published by . This book was released on 2018 with total page 156 pages. Available in PDF, EPUB and Kindle. Book excerpt: One of prominent issues related to failures in nuclear power components is attributed to material degradation due the aggressive environment conditions, and mechanical stresses. For instance, reactor core support components, such as fuel claddings, are under prolonged exposure to an intense neutron field from the fission of fuel and operate at elevated temperature under fatigue loadings caused by start-up, shut-down, and unscheduled emergency shut-down. Additionally, exposure to high-fluence neutron radiation can lead to microscopic defects that result in material hardening and embrittlement, which significantly affects the physical and mechanical properties of the materials, resulting in further reduction in fatigue life of reactor structural components. The effects of fatigue damage on material deterioration can be further exacerbated by the presence of thermal loading, hold-time, and high-temperature water coolant environments. In this study, uniaxial fatigue models were used to predict fatigue behavior based only on simple monotonic properties including ultimate tensile strength and Brinell hardness. Two existing models, the Bäumel-Seeger uniform material law and the Roessle-Fatemi hardness method, were employed and extended to include the effects of test temperature, neutron irradiation fluence, irradiation-induced helium and irradiation-induced swellings on fatigue life of austenitic stainless steels. Furthermore, a methodology to estimate fatigue crack length using a strip-yield based model is presented. This methodology is also extended to address the effect of creep deformation in a presence of hold- times, and expanded to include the effects of irradiation and water environment. Reasonable fatigue life predictions and crack growth estimations are obtained for irradiated austenitic stainless steels types 304, 304L, and 316, when compared to the experimental data available in the literature. Lastly, a failure analysis methodology of a mixer unit shaft made of AISI 304 stainless steel is also presented using a conventional 14-step failure analysis approach. The primary mode of failure is identified to be intergranular stress cracking at the heat affected zones. A means of circumventing this type of failure in the future is presented.

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1976 with total page 612 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by H. R. Brager and published by ASTM International. This book was released on 1982 with total page 1250 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1979 with total page 1254 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by and published by ASTM International. This book was released on 1981 with total page 1227 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Elastic plastic Fracture Test Methods written by E. T. Wessel and published by ASTM International. This book was released on 1985 with total page 434 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fusion Energy Update written by and published by . This book was released on 1986 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1985 with total page 1346 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book INIS Atomindex written by and published by . This book was released on 1988 with total page 962 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Energy Research Abstracts written by and published by . This book was released on 1984 with total page 636 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Fatigue Crack Growth of Low Fluence Neutron Irradiated Stainless Steel DIN 1 4948 written by MI. de Vries and published by . This book was released on 1982 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Compact-tension (CT) specimens of stainless steel DIN 1.4948, which is similar to AISI Type 304, have been irradiated up to a fluence level of 2.1024 n.m.-2 (E > 0.1 MeV) at temperatures ranging from 330 to 823 K. Post-irradiation constant-load-amplitude crack propagation (fcp) tests were performed in air at temperatures from 298 to 823 K with frequencies ranging from 10-3 to 10 Hz and R-ratios (min. load/max. load) of 0.05 and 0.30. Irradiation hardening after the low temperature irradiations (573 K and below) caused a reduction of the fatigue crack growth rate. Irradiation at the higher temperatures did not affect the fcp at the high frequency of 10 Hz. At 823 K the combination of high R-ratio and low frequency (10-2 Hz) resulted in an increase of the post-irradiation crack growth rate with a factor 10. This irradiation effect is attributed to the observed intergranular crack propagation.

Download or read book Fatigue Crack Propagation in Fast Neutron Irradiated Stainless Steels and Welds written by P. Shahinian and published by . This book was released on 1975 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: 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.