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Book Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures

Download or read book Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures written by JM. Beeston and published by . This book was released on 1970 with total page 30 pages. Available in PDF, EPUB and Kindle. Book excerpt: Uniaxial fatigue properties from tests at 400, 500, 600, and 700 C on Type 304, 304L (Ti modified), and 316 stainless steel specimens irradiated at 450 C in sodium and 750 C in argon at fluences of 0.03 to 9.3x1021 n/cm2, E>0.1 MeV, are given and compared with control specimens. Material was tested in the annealed, cold-worked, and chilled-swaged-tempered condition, while primary controls received a pretest anneal of 1500 h at 750 C. The data at 400, 500, and 600 C are compared with proposed design curves for 18-8 steels. Some data on microstructural changes due to irradiation are given. A reduction in the fatigue life by a factor of less than 2.5 was found in the annealed material, which was attributed to irradiation damage. A beneficial effect on fatigue life of pretreatment by swaging was found after irradiation at 450 and 750 C for 2550 h.

Book Mechanical Properties of Irradiated Stainless Steels

Download or read book Mechanical Properties of Irradiated Stainless Steels written by Richard E. Schreiber and published by . This book was released on 1961 with total page 112 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications

Download or read book Irradiation Effects on Structural Alloys for Nuclear Reactor Applications written by A. L. Bement and published by ASTM International. This book was released on 1971 with total page 571 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Automated Test Methods for Fatigue Crack Growth and Fracture Toughness Tests on Irradiated Stainless Steels at High Temperature

Download or read book Automated Test Methods for Fatigue Crack Growth and Fracture Toughness Tests on Irradiated Stainless Steels at High Temperature written by BAJ Schaap and published by . This book was released on 1985 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: An automated system for fatigue crack growth and fracture toughness measurements has been developed for irradiated stainless steels tested at temperatures up to 925 K. The system, including a microcomputer, is based on the d-c potential-drop technique for crack extension measurements. Specimens of the compact-tension type are used for the experiments. A description is given of the potential-drop method and the automated data acquisition system. The method of collecting N-a data pairs is given as well as the calculation and analysis of the fatigue crack growth rate (da/dN) and stress-intensity factor (?K). The measurement of load, deflection, and crack extension data to determine the J-versus-?a curves is also discussed.

Book High Temperature Fatigue

Download or read book High Temperature Fatigue written by R.P. Skelton and published by Springer Science & Business Media. This book was released on 2012-12-06 with total page 330 pages. Available in PDF, EPUB and Kindle. Book excerpt: About 35 years ago, thermal fatigue was identified as an important phenomenon which limited the lifetime of high temperature plant. In the intervening years many investigations have been carried out, primarily to give guidance on likely endurance (especially in the presence of time dependent deformation) but latterly, with the introduction of sophisticated testing machines, to provide knowledge of the underlying mechanisms of failure. A previous edited book (Fatigue at High Temperature, Elsevier Applied Science Publishers, 1983) summarised the state-of-the-art of high temperature fatigue testing and examined the factors influencing life, such as stress state, environment and microstructural effects. It also considered, in some detail, cyclic crack growth as a more rigorous approach to life limitation. The aim of the present volume (which in style and format follows exactly the same lines as its predecessor) is once again to pursue the desire to translate detailed laboratory knowledge into engineering design and assessment. There is, for example, a need to consider the limitations of the laboratory specimen and its relationship with engineering features. Many design procedures still rely on a simple endurance approach based on failure of a smooth specimen, and this is taken to indicate crack initiation in the component. In this volume, therefore, crack propagation is covered only incidentally, emphasis being placed instead on basic cyclic stress strain properties, non-isothermal behaviour, metallography, failure criteria and the need for agreed testing procedures.

Book Nuclear Science Abstracts

Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 632 pages. Available in PDF, EPUB and Kindle. Book excerpt: NSA is a comprehensive collection of international nuclear science and technology literature for the period 1948 through 1976, pre-dating the prestigious INIS database, which began in 1970. NSA existed as a printed product (Volumes 1-33) initially, created by DOE's predecessor, the U.S. Atomic Energy Commission (AEC). NSA includes citations to scientific and technical reports from the AEC, the U.S. Energy Research and Development Administration and its contractors, plus other agencies and international organizations, universities, and industrial and research organizations. References to books, conference proceedings, papers, patents, dissertations, engineering drawings, and journal articles from worldwide sources are also included. Abstracts and full text are provided if available.

Book Fatigue Life and Crack Growth Predictions of Irradiated Stainless Steels

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.

Book Fatigue  Tensile  and Relaxation Behavior of Stainless Steels

Download or read book Fatigue Tensile and Relaxation Behavior of Stainless Steels written by Joseph B. Conway and published by . This book was released on 1975 with total page 288 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fatigue Data on Precipitation hardenable Stainless Steels

Download or read book Fatigue Data on Precipitation hardenable Stainless Steels written by R. J. Favor and published by . This book was released on 1960 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1995 with total page 702 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Inventory of energy research and development  1973 1975

Download or read book Inventory of energy research and development 1973 1975 written by Oak Ridge National Laboratory and published by . This book was released on 1976 with total page 1356 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures

Download or read book Fatigue Behavior and Microstructure of Neutron Irradiated Thin Section Type 304 Stainless Steel at Elevated Temperatures written by DJ. Michel and published by . This book was released on 1975 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of high fluence fast neutron irradiation on the fatigue behavior, microstructure, swelling, and microhardness were evaluated for annealed Type 304 stainless steel which had attained fluences near 1.6 x 1023 neutrons (n)/cm2 (> 0.1 MeV) at irradiation temperatures from 370 to 470°C (698 to 878°F). Unnotched fatigue specimens remotely prepared from the irradiated material were cycled at resonance in reverse bending in air at constant amplitude at 427 and 593°C (800 and 1100°F). At 427°C, the fatigue life was found to be strongly dependent on irradiation temperature. A decrease in fatigue life from 2 x 105 to 1.1 x 104 cycles was seen with increasing irradiation temperature within the range investigated. For irradiation temperatures below approximately 427°C, the fatigue life was found to decrease with increasing fluence in the range from 1.3 x 1022 to 1.5 x 1023 n/cm2 (> 0.1 MeV). The fatigue behavior of specimens tested at 593°C was characterized by a similar irradiation temperature dependency. At 593°C, however, little effect of fluence was observed in the irradiation temperature range below 427°C. At both test temperatures the nuclear exposure produced an increase in fatigue life at irradiation temperatures below 450°C.

Book Effect of Neutron Irradiation on Fatigue Crack Propagation in Types 304 and 316 Stainless Steels at High Temperatures

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.

Book Metal Fatigue in Engineering

Download or read book Metal Fatigue in Engineering written by Ralph I. Stephens and published by John Wiley & Sons. This book was released on 2000-11-03 with total page 496 pages. Available in PDF, EPUB and Kindle. Book excerpt: Classic, comprehensive, and up-to-date Metal Fatigue in Engineering Second Edition For twenty years, Metal Fatigue in Engineering has served as an important textbook and reference for students and practicing engineers concerned with the design, development, and failure analysis of components, structures, and vehicles subjected to repeated loading. Now this generously revised and expanded edition retains the best features of the original while bringing it up to date with the latest developments in the field. As with the First Edition, this book focuses on applied engineering design, with a view to producing products that are safe, reliable, and economical. It offers in-depth coverage of today's most common analytical methods of fatigue design and fatigue life predictions/estimations for metals. Contents are arranged logically, moving from simple to more complex fatigue loading and conditions. Throughout the book, there is a full range of helpful learning aids, including worked examples and hundreds of problems, references, and figures as well as chapter summaries and "design do's and don'ts" sections to help speed and reinforce understanding of the material. The Second Edition contains a vast amount of new information, including: * Enhanced coverage of micro/macro fatigue mechanisms, notch strain analysis, fatigue crack growth at notches, residual stresses, digital prototyping, and fatigue design of weldments * Nonproportional loading and critical plane approaches for multiaxial fatigue * A new chapter on statistical aspects of fatigue

Book Axial load Fatigue Properties of PH 15 7 Mo Stainless Steel in Condition TH 1050 at Ambient Temperature and 500   F

Download or read book Axial load Fatigue Properties of PH 15 7 Mo Stainless Steel in Condition TH 1050 at Ambient Temperature and 500 F written by Walter Illg and published by . This book was released on 1964 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: Axial-load fatigue tests were conducted on notched and unnotched sheet specimens of PH 15-7 Mo stainless steel in Condition TH 1050. Fatigue lives at three mean stresses at ambient temperature (approx. 80 deg F) and at 500 deg F were determined throughout the lifetime range from 10(exp 2)to 10(exp 7) cycles. A special furnace incorporating guide plates is also described. A 500 deg F environment increased the fatigue limit but reduced the fatigue strength at short lifetimes. An effect of cyclic frequency was noted.

Book Irradiation Effects in Stainless Steels at High Temperatures

Download or read book Irradiation Effects in Stainless Steels at High Temperatures written by and published by . This book was released on 1965 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fatigue Testing of Irradiated Steels at High Temperatures

Download or read book Fatigue Testing of Irradiated Steels at High Temperatures written by G. L. Tjoa and published by . This book was released on 1983 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt: