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Book Void Swelling in Binary Fe Cr Alloys at 200 DPA

Download or read book Void Swelling in Binary Fe Cr Alloys at 200 DPA written by and published by . This book was released on 1994 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

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:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1994 with total page 1032 pages. Available in PDF, EPUB and Kindle. Book excerpt: Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems     Water Reactors

Download or read book Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors written by John H. Jackson and published by Springer. This book was released on 2018-12-20 with total page 2460 pages. Available in PDF, EPUB and Kindle. Book excerpt: This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.

Book Handbook of Nuclear Engineering

Download or read book Handbook of Nuclear Engineering written by Dan Gabriel Cacuci and published by Springer Science & Business Media. This book was released on 2010-09-14 with total page 3701 pages. Available in PDF, EPUB and Kindle. Book excerpt: This is an authoritative compilation of information regarding methods and data used in all phases of nuclear engineering. Addressing nuclear engineers and scientists at all levels, this book provides a condensed reference on nuclear engineering since 1958.

Book Microstructure of Irradiated Materials  Volume 373

Download or read book Microstructure of Irradiated Materials Volume 373 written by Ian M. Robertson and published by . This book was released on 1995-04-03 with total page 600 pages. Available in PDF, EPUB and Kindle. Book excerpt: The focus of the symposium, which was held at the 1994 MRS Fall Meeting, was on the changes produced in the microstructure of metals, ceramics, and semiconductors by irradiation with energetic particles. This proceedings volume contains invited and contributed papers. Among the topics are computer simulation of displacement cascade damage in metals; radiation effects in ceramic insulators; and computer simulation of thermal annealing effects of self implanted silicon. Annotation copyright by Book News, Inc., Portland, OR

Book Neutron Irradiation Damage in Ferrltic Fe Cr Alloys

Download or read book Neutron Irradiation Damage in Ferrltic Fe Cr Alloys written by DS. Gelles and published by . This book was released on 1990 with total page 25 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent work on microstructural development in a series of ferritic alloys following irradiation in the Fast Flux Test Facility (FFTF) is presented. the series includes Fe-Cr binary alloys ranging from 3 to 18 chromium, and substitutional ferritic alloys based on Fe-10Cr with minor additions of silicon, manganese, vanadium, tantalum, and zirconium. Irradiations were performed to fluences as high as 30 dpa at 425°C. the simple Fe-Cr binary alloy behavior following irradiation to 15 dpa was found to be similar to that observed following irradiation in EBR-II. All specimens contained radiation damage such as dislocation loops and voids. Swelling was highest, 0.26%, in the Fe-9Cr alloy with a corresponding dislocation network comprising equal parts of a?100? and a/2 ?111? Burger's vectors. Less swellings was found in other alloys with a corresponding dislocation structure composed mainly of a?100? loops. An example of a deformation slip band containing elongated voids was found, which indicated that channel fracture may occur in ferritic alloys that contain uniform void swelling.

Book Fusion Energy Update

Download or read book Fusion Energy Update written by and published by . This book was released on 1980 with total page 68 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Void Swelling in Electron Irradiated Fe Cr Ni Model Alloys

Download or read book Void Swelling in Electron Irradiated Fe Cr Ni Model Alloys written by O. Dimitrov and published by . This book was released on 1987 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: A study of the void swelling produced by 1-MeV electron irradiation in high-purity Fe-Cr-Ni alloys has been performed in order to obtain a better understanding of the composition dependence of swelling in this system. Alloys with 16 wt% chromium and 20 to 75 wt% nickel, with or without helium preinjection, were irradiated in a high-voltage electron microscope, at a displacement rate of 22 dpa/h in the temperature range 370 to 600°C, to maximum damage levels up to 105 dpa. An increase in nickel concentration was found to reduce void density, to increase incubation dose, and to shift the swelling-rate maximum to lower temperatures. A helium preinjection of 70 appm reduces strongly the effect of material composition. The application of a simple void-growth model to the experimental results shows that the changes of point-defect parameters with nickel concentration produce variations of the calculated swelling rate that exhibit the observed trends. However these variations are of only marginal amplitude, as compared with the swelling-rate variations resulting from the observed microstructural changes. The bias factor was found to decrease with decreasing temperature in the 20 wt% Ni alloy; it also decreased at 500°C, with increasing nickel concentration.

Book Metals Abstracts

Download or read book Metals Abstracts written by and published by . This book was released on 1996 with total page 764 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Comprehensive Nuclear Materials

Download or read book Comprehensive Nuclear Materials written by and published by Elsevier. This book was released on 2020-07-22 with total page 4871 pages. Available in PDF, EPUB and Kindle. Book excerpt: Materials in a nuclear environment are exposed to extreme conditions of radiation, temperature and/or corrosion, and in many cases the combination of these makes the material behavior very different from conventional materials. This is evident for the four major technological challenges the nuclear technology domain is facing currently: (i) long-term operation of existing Generation II nuclear power plants, (ii) the design of the next generation reactors (Generation IV), (iii) the construction of the ITER fusion reactor in Cadarache (France), (iv) and the intermediate and final disposal of nuclear waste. In order to address these challenges, engineers and designers need to know the properties of a wide variety of materials under these conditions and to understand the underlying processes affecting changes in their behavior, in order to assess their performance and to determine the limits of operation. Comprehensive Nuclear Materials, Second Edition, Seven Volume Set provides broad ranging, validated summaries of all the major topics in the field of nuclear material research for fission as well as fusion reactor systems. Attention is given to the fundamental scientific aspects of nuclear materials: fuel and structural materials for fission reactors, waste materials, and materials for fusion reactors. The articles are written at a level that allows undergraduate students to understand the material, while providing active researchers with a ready reference resource of information. Most of the chapters from the first Edition have been revised and updated and a significant number of new topics are covered in completely new material. During the ten years between the two editions, the challenge for applications of nuclear materials has been significantly impacted by world events, public awareness, and technological innovation. Materials play a key role as enablers of new technologies, and we trust that this new edition of Comprehensive Nuclear Materials has captured the key recent developments. Critically reviews the major classes and functions of materials, supporting the selection, assessment, validation and engineering of materials in extreme nuclear environments Comprehensive resource for up-to-date and authoritative information which is not always available elsewhere, even in journals Provides an in-depth treatment of materials modeling and simulation, with a specific focus on nuclear issues Serves as an excellent entry point for students and researchers new to the field

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1996 with total page 1192 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book The Question of Saturation of Void Swelling in Fe Cr Ni Austenitic Alloys

Download or read book The Question of Saturation of Void Swelling in Fe Cr Ni Austenitic Alloys written by FA. Garner and published by . This book was released on 2000 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt: Whereas in earlier publications it appeared that a possible saturation of neutron-induced void swelling might be developing at temperatures of 400 and 427°C in annealed Fe-Cr-Ni model alloys in a manner that was dependent on composition, data obtained at higher neutron exposures in EBR-II have led to the conclusion that such an expectation was erroneous. At all temperatures in the range 400-650°C, the neutron induced swelling eventually reaches ~1%/dpa and continues to very high swelling levels thereafter without any hint of saturation.

Book Materials for Nuclear Reactor Core Applications

Download or read book Materials for Nuclear Reactor Core Applications written by and published by . This book was released on 1987 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radiation induced Changes in Microstructure

Download or read book Radiation induced Changes in Microstructure written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 919 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Government Reports Announcements   Index

Download or read book Government Reports Announcements Index written by and published by . This book was released on 1995 with total page 776 pages. Available in PDF, EPUB and Kindle. Book excerpt: