Read Books Online and Download eBooks, EPub, PDF, Mobi, Kindle, Text Full Free.
Interactions Of Defects With Dislocations In Reactor Pressure Vessel Steels
Download Interactions Of Defects With Dislocations In Reactor Pressure Vessel Steels full books in PDF, epub, and Kindle. Read online Interactions Of Defects With Dislocations In Reactor Pressure Vessel Steels ebook anywhere anytime directly on your device. Fast Download speed and no annoying ads. We cannot guarantee that every ebooks is available!
Book Synopsis Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels by : O. Mercier
Download or read book Interactions of Defects with Dislocations in Reactor Pressure Vessel Steels written by O. Mercier and published by . This book was released on 1993 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The radiation embrittlement of reactor pressure vessel steels may be partially explained by the creation of irradiation-induced defects that interact with the moving dislocations during plastic deformation. This research studies the nature of the interaction mechanisms and the microstructural properties and the mobility of the dislocations.
Book Synopsis Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels by : Lendell E. Steele
Download or read book Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels written by Lendell E. Steele and published by ASTM International. This book was released on 1993 with total page 405 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Deformation Behavior in Reactor Pressure Vessel Steels as a Clue to Understanding Irradiation Hardening by :
Download or read book Deformation Behavior in Reactor Pressure Vessel Steels as a Clue to Understanding Irradiation Hardening written by and published by . This book was released on 1999 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: In this paper, we examine the post-yield true stress vs true strain behavior of irradiated pressure vessel steels and iron-based alloys to reveal differences in strain-hardening behavior associated with different irradiating particles (neutrons and electrons) and different alloy chernky. It is important to understand the effects on mechanical properties caused by displacement producing radiation of nuclear reactor pressure steels. Critical embrittling effects, e.g. increases in the ductile-to-brittle-transition-temperature, are associated with irradiation-induced increases in yield strength. In addition, fatigue-life and loading-rate effects on fracture can be related to the post-irradiation strain-hardening behavior of the steels. All of these properties affect the expected service life of nuclear reactor pressure vessels. We address the characteristics of two general strengthening effects that we believe are relevant to the differing defect cluster characters produced by neutrons and electrons in four different alloys: two pressure vessel steels, A212B and A350, and two binary alloys, Fe-0.28 wt%Cu and Fe-0.74 wt%Ni. Our results show that there are differences in the post-irradiation mechanical behavior for the two kinds of irradiation and that the differences are related both to differences in damage produced and alloy chemistry. We find that while electron and neutron irradiations (at T (less-than or equal to) 60 C) of pressure vessel steels and binary iron-based model alloys produce similar increases in yield strength for the same dose level, they do not result in the same post-yield hardening behavior. For neutron irradiation, the true stress flow curves of the irradiated material can be made to superimpose on that of the unirradiated material, when the former are shifted appropriately along the strain axis. This behavior suggests that neutron irradiation hardening has the same effect as strain hardening for all of the materials analyzed. For electron irradiated steels, the post-yield hardening rate is clearly greater than that of the unirradiated material, and the flow curves cannot be made to superimpose. The binary iron-base model alloys studied here show a less pronounced difference in flow behavior for neutrons and electrons than exhibited by the steels, implicating the effect of alloy chemistry. Our results are analyzed in the context of classical theories dealing with the interaction between the deformation microstructure, i.e. glide dislocations, and irradiation-produced defects. Our findings provide clues about the way different alloy constituents interact with the different kinds of irradiation damage to strengthen the material differently.
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1975 with total page 900 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 Synopsis Property Changes Resulting from Impurity-Defect Interactions in Iron and Pressure Vessel Steel Alloys by : FA. Smidt
Download or read book Property Changes Resulting from Impurity-Defect Interactions in Iron and Pressure Vessel Steel Alloys written by FA. Smidt and published by . This book was released on 1973 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of 0.3 atomic percent copper, vanadium, nickel, and phosphorus and 0.1 atomic percent carbon addition on the irradiation response of pure iron have been investigated to clarify the role of copper and phosphorus in embrittlement of pressure vessel steels. Compression tests and transmission electron microscopy (TEM) analysis of the aforementioned alloys and selected heats of pressure vessel steel and weldment have been examined after irradiation to fluences of 2.5 x 1019 and 4.5 x 1020 n/cm2 > 1 MeV at 290 C (550 F). Copper is found to influence the properties by promoting nucleation of defect aggregates, probably vacancy loops, at low fluences, thus increasing the radiation strengthening and shifting the transition temperature upward. Small voids were observed in the 0.3Ni, 0.3Cu, and 0.1C alloys and in pure iron but not in 0.3V or 0.3P alloys.
Book Synopsis Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants by : Naoki Soneda
Download or read book Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants written by Naoki Soneda and published by Elsevier. This book was released on 2014-09-01 with total page 437 pages. Available in PDF, EPUB and Kindle. Book excerpt: Reactor Pressure Vessels (RPVs) contain the fuel and therefore the reaction at the heart of nuclear power plants. They are a life-determining structural component: if they suffer serious damage, the continued operation of the plant is in jeopardy. This book critically reviews irradiation embrittlement, the main degradation mechanism affecting RPV steels, and mitigation routes for managing the RPV lifetime. Part I reviews RPV design and fabrication in different countries, with an emphasis on the materials required, their important properties, and manufacturing technologies. Part II then considers RVP embrittlement in operational nuclear power plants using different reactors. Chapters are devoted to embrittlement in light-water reactors, including WWER-type reactors and Magnox reactors. Finally, Part III presents techniques for studying embrittlement, including irradiation simulation techniques, microstructural characterisation techniques, and probabilistic fracture mechanics. Irradiation Embrittlement of Reactor Pressure Vessels (RPVs) in Nuclear Power Plants provides a thorough review of an issue that is central to the safety of nuclear power generation. The book includes contributions from an international team of experts, and will be a useful resource for nuclear plant operators and managers, relevant regulatory and safety bodies, nuclear metallurgists and other academics in this field Discusses reactor pressure vessel (RPV) design and the effect irradiation embrittlement can have, the main degradation mechanism affecting RPVs Examines embrittlement processes in RPVs in different reactor types, as well as techniques for studying RPV embrittlement
Book Synopsis Dislocation Mechanism-Based Crystal Plasticity by : Zhuo Zhuang
Download or read book Dislocation Mechanism-Based Crystal Plasticity written by Zhuo Zhuang and published by Academic Press. This book was released on 2019-04-12 with total page 450 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dislocation Based Crystal Plasticity: Theory and Computation at Micron and Submicron Scale provides a comprehensive introduction to the continuum and discreteness dislocation mechanism-based theories and computational methods of crystal plasticity at the micron and submicron scale. Sections cover the fundamental concept of conventional crystal plasticity theory at the macro-scale without size effect, strain gradient crystal plasticity theory based on Taylar law dislocation, mechanism at the mesoscale, phase-field theory of crystal plasticity, computation at the submicron scale, including single crystal plasticity theory, and the discrete-continuous model of crystal plasticity with three-dimensional discrete dislocation dynamics coupling finite element method (DDD-FEM). Three kinds of plastic deformation mechanisms for submicron pillars are systematically presented. Further sections discuss dislocation nucleation and starvation at high strain rate and temperature effect for dislocation annihilation mechanism. Covers dislocation mechanism-based crystal plasticity theory and computation at the micron and submicron scale Presents crystal plasticity theory without size effect Deals with the 3D discrete-continuous (3D DCM) theoretic and computational model of crystal plasticity with 3D discrete dislocation dynamics (3D DDD) coupling finite element method (FEM) Includes discrete dislocation mechanism-based theory and computation at the submicron scale with single arm source, coating micropillar, lower cyclic loading pillars, and dislocation starvation at the submicron scale
Book Synopsis Radiation Damage of Structural Materials by : J. Koutský
Download or read book Radiation Damage of Structural Materials written by J. Koutský and published by Elsevier. This book was released on 2013-10-22 with total page 362 pages. Available in PDF, EPUB and Kindle. Book excerpt: Maintaining the integrity of nuclear power plants is critical in the prevention or control of severe accidents. This monograph deals with both basic groups of structural materials used in the design of light-water nuclear reactors, making the primary safety barriers of NPPs. Emphasis is placed on materials used in VVER-type nuclear reactors: Cr-Mo-V and Cr-Ni-Mo-V steel for RPV and Zr-Nb alloys for fuel element cladding. The book is divided into 7 main chapters, with the exception of the opening one and the chapter providing a phenomenological background for the subject of radiation damage. Chapters 3-6 are devoted to RPV steels and chapters 7-9 to zirconium alloys, analysing their radiation damage structure, changes of mechanical properties due to neutron irradiation as well as factors influencing the degree of their performance degradation. The recovery of damaged materials is also discussed. Considerable attention is paid to a comparison of VVER-type and western-type light-water materials. This monograph will be of great value to postgraduate students in nuclear engineering and materials science, and for designers and research workers in nuclear energy.
Book Synopsis Material Research in Atomic Scale by Mössbauer Spectroscopy by : Miroslav Mashlan
Download or read book Material Research in Atomic Scale by Mössbauer Spectroscopy written by Miroslav Mashlan and published by Springer Science & Business Media. This book was released on 2003-03-31 with total page 380 pages. Available in PDF, EPUB and Kindle. Book excerpt: Proceedings of the NATO Advanced Research Workshop, held in Smolenice, Slovak Republic, 1-6 June 2002
Download or read book Applied Mechanics Reviews written by and published by . This book was released on 2000 with total page 680 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly by :
Download or read book Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly written by and published by . This book was released on 2015 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: The integrity of reactor pressure vessels (RPVs) is of utmost importance to ensure safe operation of nuclear reactors under extended lifetime. Microstructure scale models at various length and time scales, coupled concurrently or through homogenization methods, can play a crucial role in understanding and quantifying irradiation induced defect production, growth and their influence on mechanical behavior of RPV steels. A multi-scale approach, involving atomistic, meso-and engineering scale models, is currently being pursued within the GRIZZLY project to understand and quantify irradiation induced embrittlement of RPV steels. Within this framework, a dislocation-density based crystal plasticity model has been de- veloped in GRIZZLY that captures the effect of irradation induced defects on the flow stress behavior and is presented in this report. The present formulation accounts for the interaction between self-interstitial loops and matrix dislocations. The model predictions have been validated with experiments and disloca- tion dynamics simulation.
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1991 with total page 910 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels by : Lendell E. Steele
Download or read book Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels written by Lendell E. Steele and published by ASTM International. This book was released on 1983 with total page 240 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Structural Integrity of Light Water Reactor Pressure Boundary Components by : Materials Engineering Associates
Download or read book Structural Integrity of Light Water Reactor Pressure Boundary Components written by Materials Engineering Associates and published by . This book was released on 1984 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Fracture, Plastic Flow and Structural Integrity in the Nuclear Industry by : P. B. Hirsch
Download or read book Fracture, Plastic Flow and Structural Integrity in the Nuclear Industry written by P. B. Hirsch and published by CRC Press. This book was released on 2019-11-11 with total page 237 pages. Available in PDF, EPUB and Kindle. Book excerpt: This volume brings together the papers presented at the 7th Symposium organised by the Technical Advisory Group on Structural Integrity of Nuclear Plant (TAGS!) which was held at the TWI Conference Centre, Great Abington, UK on 29 April 1999. The Symposium, which marked 25 years of TAGSI and its predecessor, the Light Water Reactor Study Group (LWRSG), was dedicated to Sir Alan Cottrell FREng, FRS, whose impact on the fields of integrity, reliability and safety of engineering structures and components has been second to none.
Book Synopsis Effects of Radiation on Materials by : Margaret L. Hamilton
Download or read book Effects of Radiation on Materials written by Margaret L. Hamilton and published by ASTM International. This book was released on 2000 with total page 1266 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: