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Book Effects of Helium Content on Microstructural Development in Type 316 Stainless Steel Under Neutron Irradiation

Download or read book Effects of Helium Content on Microstructural Development in Type 316 Stainless Steel Under Neutron Irradiation written by Philip James Maziasz and published by . This book was released on 1984 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Helium Content of Microstructural Development in Type 316 Stainless Steel Under Neutron Irradiation

Download or read book Effects of Helium Content of Microstructural Development in Type 316 Stainless Steel Under Neutron Irradiation written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work investigated the sensitivity of microstructural evolution, particularly precipitate development, to increased helium content during thermal aging and during neutron irradiation. Helium (110 at. ppM) was cold preinjected into solution annealed (SA) DO-heat type 316 stainess steel (316) via cyclotron irradiation. These specimens were then exposed side by side with uninjected samples. Continuous helium generation was increased considerably relative to EBR-II irradiation by irradiation in HFIR. Data were obtained from quantitative analytical electron microscopy (AEM) in thin foils and on extraction replicas. 480 refs., 86 figs., 19 tabs.

Book Swelling  Microstructural Development and Helium Effects in Type 316 Stainless Steel Irradiated in HFIR and EBR II

Download or read book Swelling Microstructural Development and Helium Effects in Type 316 Stainless Steel Irradiated in HFIR and EBR II written by and published by . This book was released on 1981 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work examines the swelling and microstructural development of a single heat of 20%-cold-worked type 316 stainless steel irradiated to produce displacement damage and a high, continuous helium generation rate, in the High Flux Isotope Reactor (HFIR). Similar irradiation of the same heat of steel in the Experimental Breeder Reactor (EBR)-II is used as a base line for comparing displacement damage accompanying a very low continuous helium generation rate. At temperatures above and below the void swelling regime (approx. 350 to 625°C) swelling is greater in HFIR than in EBR-II. In the temprature range of 350 to 625°C, cavity formation, precipitation and dislocation recovery are both enhanced and accelerated in HFIR, often causing swelling at lower dose than in EBR-II. In HFIR, however, cavities appear to be bubbles rather than voids. They are about 10 times smaller and 20 to 50 times more numerous than voids in EBR-II. Thus, the swelling becomes greater in EBR-II than in HFIR for 20%-CW 316 in the void swelling temperature ranges as fluence increases. Such differences in swelling and microstructural behavior must be understood in order to anticipate the behavior of materials during fusion irradiation.

Book Effect of Preinjected Helium on Swelling and Microstructure of Neutron Irradiated Pressurized Tubes of Type 316 Stainless Steel

Download or read book Effect of Preinjected Helium on Swelling and Microstructure of Neutron Irradiated Pressurized Tubes of Type 316 Stainless Steel written by A. Hishinuma and published by . This book was released on 1982 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Microstructures of helium preinjected, pressurized tube specimens of 22% cold-worked type 316 stainless steel have been examined after neutron irradiation in EBR-II at 525°C to a dose of 23 dpa under a stress of 32 MPa. Preinjected helium at 20 and 60 appm suppressed the swelling. The degree of suppression increased with increasing amounts of preinjected helium. The uninjected sample areas contained a unimodal distribution of cavities, including the largest cavities observed. A bimodal cavity distribution containing a large number density of small cavities and a smaller number density of larger cavities was found. The large number of fine cavities found in the preinjected sections are believed to change the ratio of cavity to dislocation sink strengths and to reduce the bias, resulting in a reduction of the cavity growth rate. The principal precipitate formed during irradiation of the stressed tube specimens was eta phase.

Book Nuclear Science Abstracts

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:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1993 with total page 420 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 1986 with total page 992 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 Irradiation Effects on the Microstructure and Properties of Metals

Download or read book Irradiation Effects on the Microstructure and Properties of Metals written by and published by ASTM International. This book was released on 1976 with total page 491 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book MiCon 86

    Book Details:
  • Author : B. L. Bramfitt
  • Publisher : ASTM International
  • Release : 1988
  • ISBN : 0803109857
  • Pages : 324 pages

Download or read book MiCon 86 written by B. L. Bramfitt and published by ASTM International. This book was released on 1988 with total page 324 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fusion Energy Update

Download or read book Fusion Energy Update written by and published by . This book was released on 1979 with total page 112 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 N. H. Packan and published by ASTM International. This book was released on 1990 with total page 679 pages. Available in PDF, EPUB and Kindle. Book excerpt: Annotation Effects of Radiation on Materials: Fourteenth International Symposium was presented at Andover, MA, June 1988. The symposium was sponsored by ASTM Committee E-10 on Nuclear Technology and Applications. The papers from the first three days of the symposium appear in the two volumes of this publication. Volume I encompasses radiation damage- induced microstructures; point defect, solute, and gas atom effects; atomic-level measurement techniques; and applications of theory. Volume II includes mechanical behavior, all papers dealing with pressure-vessel steels, breeder reactor components, dosimetry, and nuclear fuels. The fourth day of the symposium was devoted to the single topic of reduced-activation materials (see TK9204). The two volumes are separately sold at $127 and $128 respectively; each is independently indexed. Annotation copyrighted by Book News, Inc., Portland, OR.

Book Effects of Radiation on Materials

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:

Book INIS Atomindex

Download or read book INIS Atomindex written by and published by . This book was released on 1986 with total page 1260 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Fundamental Aspects of Inert Gases in Solids

Download or read book Fundamental Aspects of Inert Gases in Solids written by S.E. Donnelly and published by Springer. This book was released on 2013-12-20 with total page 458 pages. Available in PDF, EPUB and Kindle. Book excerpt: The NATO Advanced Research Workshop on Fundamental Aspects of Inert Gases in Solids, held at Bonas, France from 16-22 September 1990, was the fifth in a series of meetings that have been held in this topic area since 1979. The Consultants' Meeting in that year at Harwell on Rare Gas Behaviour in Metals and Ionic Solids was followed in 1982 by the Jiilich Inter national Symposium on Fundamental Aspects of Helium in Metals. Two smaller meetings have followed-a CECAM organised workshop on Helium Bubbles in Metals was held at Orsay, France in 1986 while in February 1989, a Topical Symposium on Noble Gases in Metals was held in Las Vegas as part of the large TMS/AIME Spring Meeting. As is well known, the dominating feature of inert gas atoms in most solids is their high heat of solution, leading in most situations to an essentially zero solubility and gas-atom precipita tion. In organising the workshop, one particular aim was to target the researchers in the field of inert-gas/solid interactions from three different areas--namely metals, tritides and nuclear fuels-in order to encourage and foster the cross-fertilisation of approaches and ideas. In these three material classes, the behaviour of inert gases in metals has probably been most studied, partly from technological considerations-the effects of helium production via (n, a) reac tions during neutron irradiation are of importance, particularly in a fusion reactor environ ment-and partly from a more fundamental viewpoint.

Book Effects of Radiation on Materials

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:

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