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Book Methods for Incorporating the Effects of LWR Coolant Environments in Pressure Vessel and Piping Fatigue Evaluations

Download or read book Methods for Incorporating the Effects of LWR Coolant Environments in Pressure Vessel and Piping Fatigue Evaluations written by and published by . This book was released on 2002 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper summarizes the work performed at Argonne National Laboratory on the fatigue of piping and pressure vessel steels in the coolant environments of light water reactors. The existing fatigue strain vs. life ({var_epsilon}-N) data were evaluated to establish the effects of various material and loading variables, such as steel type, strain range, strain rate, temperature, and dissolved-oxygen level in water, on the fatigue lives of these steels. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for carbon and low-alloy steels and austenitic stainless steels as a function of material, loading, and environment variables. Case studies of fatigue failures in nuclear power plants are presented, and the contribution of environmental effects to crack initiation is discussed. Methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the possible conservatism in the existing fatigue design curves of the ASME Code.

Book Methods for Incorporating Effects of LWR Coolant Environment Into ASME Code Fatigue Evaluations

Download or read book Methods for Incorporating Effects of LWR Coolant Environment Into ASME Code Fatigue Evaluations written by and published by . This book was released on 1999 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Appendix I to Section HI of the Code specifies design fatigue curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Recent test data illustrate potentially significant effects of LWR environments on the fatigue resistance of carbon and low-alloy steels and austenitic stainless steels (SSs). Under certain loading and environmental conditions, fatigue lives of carbon and low-alloy steels can be a factor of (almost equal to)70 lower in an LWR environment than in air. These results raise the issue of whether the design fatigue curves in Section III are appropriate for the intended purpose. This paper presents the two methods that have been proposed for incorporating the effects of LWR coolant environments into the ASME Code fatigue evaluations. The mechanisms of fatigue crack initiation in carbon and low-alloy steels and austenitic SSs in LWR environments are discussed.

Book Methods for Incorporating the Effects of LWR Coolant Environments in Pressure Vessel and Piping Fatique Evaluation

Download or read book Methods for Incorporating the Effects of LWR Coolant Environments in Pressure Vessel and Piping Fatique Evaluation written by O. K. Chopra and published by . This book was released on 2002 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Proceedings of the ASME Pressure Vessels and Piping Conference  2005  Codes and standards

Download or read book Proceedings of the ASME Pressure Vessels and Piping Conference 2005 Codes and standards written by and published by American Society of Mechanical Engineers. This book was released on 2005 with total page 410 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments

Download or read book Mechanism and Estimation of Fatigue Crack Initiation in Austenitic Stainless Steels in LWR Environments written by and published by . This book was released on 2002 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. Figures I-9.1 through I-9.6 of Appendix I to Section III of the Code specify fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of fatigue crack initiation in austenitic stainless steels in LWR coolant environments. The existing fatigue {var_epsilon}-N data have been evaluated to establish the effects of key material, loading, and environmental parameters (such as steel type, strain range, strain rate, temperature, dissolved-oxygen level in water, and flow rate) on the fatigue lives of these steels. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves for austenitic stainless steels as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are presented. The influence of reactor environments on the mechanism of fatigue crack initiation in these steels is also discussed.

Book Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems   Water Reactors

Download or read book Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors written by Gabriell Ilevbare and published by Springer. This book was released on 2017-07-17 with total page 2354 pages. Available in PDF, EPUB and Kindle. Book excerpt: This 15th Edition of the International Conference on Materials Degradation in Light Water Reactors focuses on subject areas critical to the safe and efficient running of nuclear reactor systems through the exchange and discussion of reseach results as well as field operating and management experience.

Book Design and Analysis of Pressure Vessels and Piping

Download or read book Design and Analysis of Pressure Vessels and Piping written by Dennis K. Williams and published by . This book was released on 2003 with total page 198 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fatigue Assessment in Light Water Reactors for Long Term Operation

Download or read book Fatigue Assessment in Light Water Reactors for Long Term Operation written by IAEA and published by International Atomic Energy Agency. This book was released on 2023-04-27 with total page 168 pages. Available in PDF, EPUB and Kindle. Book excerpt: Fatigue is a major element in time limited ageing analysis for long term operation of nuclear power plants (NPPs). It is important to understand how cracks occur and grow as a result of fatigue, and then assess fatigue failure. In the design and operating phase of NPPs, it is essential to consider the concurrent loadings associated with the design transients, thermal stratification, seismically induced stress cycles, and all relevant loads due to the various operational modes. After repeated cyclic loading, crack initiation can occur at the most highly affected locations if sufficient localized micro-structural damage has accumulated. This publication provides practical guidelines on how to identify and manage fatigue issues in NPPs. It explains the mechanism of fatigue, identifies which elements are the major contributors, and details how fatigue can be minimized in the design phase for new NPPs.

Book Proceedings of the 23rd Pacific Basin Nuclear Conference  Volume 2

Download or read book Proceedings of the 23rd Pacific Basin Nuclear Conference Volume 2 written by Chengmin Liu and published by Springer Nature. This book was released on 2023-05-16 with total page 1238 pages. Available in PDF, EPUB and Kindle. Book excerpt: “This is the second in a series of three volumes of proceedings of the 23rd Pacific Basin Nuclear Conference (PBNC 2022) which was held by Chinese Nuclear Society. As one in the most important and influential conference series of nuclear science and technology, the 23rd PBNC was held in Beijing and Chengdu, China in 2022 with the theme “Nuclear Innovation for Zero-carbon Future”. For taking solid steps toward the goals of achieving peak carbon emissions and carbon neutrality, future-oriented nuclear energy should be developed in an innovative way for meeting global energy demands and coordinating the deployment mechanism. It brought together outstanding nuclear scientists and technical experts, senior industry executives, senior government officials and international energy organization leaders from all across the world. The proceedings highlight the latest scientific, technological and industrial advances in Nuclear Safety and Security, Operations and Maintenance, New Builds, Waste Management, Spent Fuel, Decommissioning, Supply Capability and Quality Management, Fuel Cycles, Digital Reactor and New Technology, Innovative Reactors and New Applications, Irradiation Effects, Public Acceptance and Education, Economics, Medical and Biological Applications, and also the student program that intends to raise students’ awareness in fully engaging in this career and keep them updated on the current situation and future trends. These proceedings are not only a good summary of the frontiers in nuclear science and technology, but also a useful guideline for the researchers, engineers and graduate students.

Book Probabilistic and Environmental Aspects of Fracture and Fatigue

Download or read book Probabilistic and Environmental Aspects of Fracture and Fatigue written by Sharif Rahman and published by . This book was released on 1999 with total page 290 pages. Available in PDF, EPUB and Kindle. Book excerpt: Contains 24 papers from an August 1999 conference, organized in two sections on probabilistic fatigue, fracture, and reliability, and environmental fractures and fatigue life. Papers present novel analytical and experimental methods related to fatigue, fracture mechanics, and environmental factors f

Book Companion Guide to the ASME Boiler   Pressure Vessel Code

Download or read book Companion Guide to the ASME Boiler Pressure Vessel Code written by K. R. Rao and published by American Society of Mechanical Engineers. This book was released on 2006 with total page 872 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is Volume 2 of the fully revised second edition. Organized to provide the technical professional with ready access to practical solutions, this revised, three-volume, 2,100-page second edition brings to life essential ASME Codes with authoritative commentary, examples, explanatory text, tables, graphics, references, and annotated bibliographic notes. This new edition has been fully updated to the current 2004 Code, except where specifically noted in the text. Gaining insights from the 78 contributors with professional expertise in the full range of pressure vessel and piping technologies, you find answers to your questions concerning the twelve sections of the ASME Boiler and Pressure Vessel Code, as well as the B31.1 and B31.3 Piping Codes. In addition, you find useful examinations of special topics including rules for accreditation and certification; perspective on cyclic, impact, and dynamic loads; functionality and operability criteria; fluids; pipe vibration; stress intensification factors, stress indices, and flexibility factors; code design and evaluation for cyclic loading; and bolted-flange joints and connections.

Book Review of the Margins for ASME Code Fatigue Design Curve   Effects of Surface Roughness and Material Variability

Download or read book Review of the Margins for ASME Code Fatigue Design Curve Effects of Surface Roughness and Material Variability written by and published by . This book was released on 2003 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The ASME Boiler and Pressure Vessel Code provides rules for the construction of nuclear power plant components. The Code specifies fatigue design curves for structural materials. However, the effects of light water reactor (LWR) coolant environments are not explicitly addressed by the Code design curves. Existing fatigue strain-vs.-life ({var_epsilon}-N) data illustrate potentially significant effects of LWR coolant environments on the fatigue resistance of pressure vessel and piping steels. This report provides an overview of the existing fatigue {var_epsilon}-N data for carbon and low-alloy steels and wrought and cast austenitic SSs to define the effects of key material, loading, and environmental parameters on the fatigue lives of the steels. Experimental data are presented on the effects of surface roughness on the fatigue life of these steels in air and LWR environments. Statistical models are presented for estimating the fatigue {var_epsilon}-N curves as a function of the material, loading, and environmental parameters. Two methods for incorporating environmental effects into the ASME Code fatigue evaluations are discussed. Data available in the literature have been reviewed to evaluate the conservatism in the existing ASME Code fatigue evaluations. A critical review of the margins for ASME Code fatigue design curves is presented.

Book Pressure Vessels and Piping Codes and Standards

Download or read book Pressure Vessels and Piping Codes and Standards written by and published by . This book was released on 2004 with total page 426 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fatigue  Environmental Factors  and New Materials

Download or read book Fatigue Environmental Factors and New Materials written by Hardayal S. Mehta and published by . This book was released on 1998 with total page 396 pages. Available in PDF, EPUB and Kindle. Book excerpt: Comprises 40 papers from the July 1998 Conference. Topics include piping and vessel evaluations (mathematical modeling of weld and residual stresses, behavior of vessel cladding, and the treatment of extrusion pressures); fatigue in piping and pressure vessels (refinery RPG bullets, biaxial fatigue crack propagation, effect of machining procedures on fatigue behavior of PWR piping, fatigues of butt welded pipes, and notched stainless steel specimens); fatigue and environmental factors (effects of strain rate, oxygen, and temperature); and new and high temperature materials. Contains an author index but no subject index. Annotation copyrighted by Book News, Inc., Portland, OR