Download or read book Localized Ductility of Irradiated Zircaloy 2 Cladding in Air and Iodine Environments written by DS. Tomalin and published by . This book was released on 1977 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: A laboratory testing method which is capable of imposing plane-stress and localized plane-strain loading conditions on tubing specimens was used to examine effects of annealing temperature and test environment on the strength and ductility of neutron irradiated Zircaloy-2 tubing. Tests were performed at 350°C in both air and iodine environments on specimens previously irradiated at 327°C in a helium atmosphere to fluences ranging between 1.26 and 1.60 x 1021 neutrons (n)/cm2 (E > 1 MeV). The tensile ductility under plane-strain loading conditions depended on preirradiation annealing temperature, with recrystallized specimens showing the largest plastic strain at maximum load (6 to 10 percent) in air. By way of comparison, stress-relieved specimens showed the largest plastic strain at maximum load (4 to 5 percent) under conditions of plane-stress loading in air. An iodine environment reduced the load-carrying capacity of the cladding (plane-strain loading) and lowered the strain at maximum load to near the detection limit of the test technique (approximately 1 percent), regardless of prior heat treatment. A change in failure mode from dimpled ductile rupture to quasicleavage and fluting accompanied this loss of ductility.
Download or read book Zirconium in the Nuclear Industry written by ASTM Committee B-10 on Reactive and Refractory Metals and Alloys and published by ASTM International. This book was released on 1977 with total page 694 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book NUREG CR written by U.S. Nuclear Regulatory Commission and published by . This book was released on 1979 with total page 160 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Zirconium in the Nuclear Industry written by and published by . This book was released on 1977 with total page 700 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ASTM Special Technical Publication written by and published by . This book was released on 1977 with total page 696 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Ductility Loss of Ion Irradiated Zircaloy 2 in Iodine Environment written by H. Kamei and published by . This book was released on 1981 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: An ion bombardment simulation technique for neutron irradiation was applied to "thick" materials to study the effect of radiation damage on the ductility change in Zircaloy-2 in an iodine environment. Specimens were prepared from actual cladding tubes and, prior to the irradiation, they were heat-treated in vacuo at 450, 580, and 700°C for 2 h. Irradiation was performed by 52-MeV alpha particles up to the 0.32 displacements per atom (dpa) at 340°C. The ion beam for this energy penetrates through the specimen, leaving only the radiation damage within the target materials. In some cases, 100-MPa axial stress was applied during irradiation to examine the stress effect on plastic strain behavior after irradiation. The uniaxial tension test for postirradiation examination was carried out in a 4-torr iodine partial pressure at 6 x 10-4/min strain rate and at 350°C temperature. Similar tests were also conducted in argon gas environment, as a reference. Ductility loss begins to appear after 0.03 dpa irradiation, both in iodine and argon gas environments. The iodine presence resulted in ductility reduction, compared with the argon result in all irradiation dose ranges examined. The ductility change in the iodine environment depended on preirradiation annealing temperature up to 0.16 dpa, with 580°C specimens showing the largest plastic strain. At higher dose range, however, the ductility approached a saturation value and the difference in preirradiation annealing seemed to diminish. The stress applied during irradiation caused ductility loss to commence at lower dosage than in the case of stress-free irradiation. These results are discussed in relation to the existing stress corrosion cracking models.
Download or read book Materials Ageing and Degradation in Light Water Reactors written by K L Murty and published by Elsevier. This book was released on 2013-02-18 with total page 441 pages. Available in PDF, EPUB and Kindle. Book excerpt: Light water reactors (LWRs) are the predominant class of nuclear power reactors in operation today; however, ageing and degradation can influence both their performance and lifetime. Knowledge of these factors is therefore critical to safe, continuous operation. Materials ageing and degradation in light water reactors provides a comprehensive guide to prevalent deterioration mechanisms, and the approaches used to handle their effects.Part one introduces fundamental ageing issues and degradation mechanisms. Beginning with an overview of ageing and degradation issues in LWRs, the book goes on to discuss corrosion in pressurized water reactors and creep deformation of materials in LWRs. Part two then considers materials' ageing and degradation in specific LWR components. Applications of zirconium alloys in LWRs are discussed, along with the ageing of electric cables. Materials management strategies for LWRs are then the focus of part three. Materials management strategies for pressurized water reactors and VVER reactors are considered before the book concludes with a discussion of materials-related problems faced by LWR operators and corresponding research needs.With its distinguished editor and international team of expert contributors, Materials ageing and degradation in light water reactors is an authoritative review for anyone requiring an understanding of the performance and durability of this type of nuclear power plant, including plant operators and managers, nuclear metallurgists, governmental and regulatory safety bodies, and researchers, scientists and academics working in this area. - Introduces the fundamental ageing issues and degradation mechanisms associated with this class of nuclear power reactors - Considers materials ageing and degradation in specific light water reactor components, including properties, performance and inspection - Chapters also focus on material management strategies
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
Download or read book Oxidation and the Testing of Turbine Oils written by Cyril A. Migdal and published by ASTM International. This book was released on 2008 with total page 929 pages. Available in PDF, EPUB and Kindle. Book excerpt: This work presents papers from a December 2005 symposium held in Norfolk, Virginia, and sponsored by ASTM Committee D2 on Petroleum Products and Lubricants and its Subcommittees D02.09 on Oxidation and D02.C0 on Turbine Oils. Contributors include equipment manufacturers, end users, lubricant producers, lubricant additive suppliers, test equipment manufacturers, and standard test method developers. They share information on industry trends, evolving technologies, and changing equipment designs and operating conditions, with a focus on how these factors impact oxidation. Some topics covered include turbine oil performance limits, a new form of the rotating pressure vessel oxidation test, and degradation mechanisms leading to sludge and varnish in modern turbine oil formulations. B&w photos are included. There is no subject index. Migdal is affiliated with Chemtura Corporation.
Download or read book Five year Index to ASTM Technical Papers and Reports written by American Society for Testing and Materials and published by . This book was released on 1976 with total page 408 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Zirconium in the Nuclear Industry written by J. H. Schemel and published by ASTM International. This book was released on 1979 with total page 656 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Embrittlement by Liquid and Solid Metals written by M. H. Kamdar and published by . This book was released on 1984 with total page 618 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 1985 with total page 1218 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Pellet cladding Interaction Failures in Water Reactor Fuel Rods written by Bernardo N. Nobrega and published by . This book was released on 1981 with total page 270 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book PCI Fuel Failure Analysis written by and published by . This book was released on 1979 with total page 152 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Localized Ductility Method for Evaluating Zircaloy 2 Cladding written by LF. Coffin and published by . This book was released on 1979 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The localized ductility method has been shown to be a useful laboratory method for evaluating the mechanical performance of fuel cladding under conditions that approximate that of pellet-clad interaction (PCI). Using the method on unirradiated annealed and cold-worked cladding, performance is determined in flowing gaseous iodine and cesium plus cadmium liquid metal. In the case of iodine, increasing temperature and decreasing strain rate enhance the embrittlement, as does a texture in which the basal pole is in the direction of the applied stress. Further, microcracking is not found to occur below a finite plastic strain. The behavior is consistent with a film rupture mechanism for chemical-assisted cracking. For cesium plus cadmium, cracking is found in Zircaloy-2 above a threshold level of stress as indicated by the performance of constant crosshead and predefected constant load tests.
Download or read book EPRI NP written by and published by . This book was released on 19?? with total page 226 pages. Available in PDF, EPUB and Kindle. Book excerpt:
