Deformation and Fracture Properties of Neutron-Irradiated Recrystallized Zircaloy-2 Cladding Under Uniaxial Tension PDF Download
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Author: T. Yasuda
Publisher:
ISBN:
Category : Elasticity
Languages : en
Pages : 14
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Book Description
Sufficient evaluation of the changes in mechanical properties, such as elastic, plastic, and failure properties, due to neutron irradiation in service is required to precisely predict fuel performance. This paper presents the results of the uniaxial tensile tests performed for recrystallized (850 K, 2.5 h) Zircaloy-2 claddings irradiated in commercial BWRs to fluences of 5 x 1023 to 4 x 1025 n/m2 (E > 1 MeV). The material constants of irradiated Zircaloy-2 were obtained precisely, using a high temperature elongation detector in a hot-cell and computer analyses of digital stress-strain data.
Author: T. Yasuda
Publisher:
ISBN:
Category : Elasticity
Languages : en
Pages : 14
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Book Description
Sufficient evaluation of the changes in mechanical properties, such as elastic, plastic, and failure properties, due to neutron irradiation in service is required to precisely predict fuel performance. This paper presents the results of the uniaxial tensile tests performed for recrystallized (850 K, 2.5 h) Zircaloy-2 claddings irradiated in commercial BWRs to fluences of 5 x 1023 to 4 x 1025 n/m2 (E > 1 MeV). The material constants of irradiated Zircaloy-2 were obtained precisely, using a high temperature elongation detector in a hot-cell and computer analyses of digital stress-strain data.
Author: Leo F. P. Van Swam
Publisher: ASTM International
ISBN: 0803111991
Category : Nuclear fuel claddings
Languages : en
Pages : 781
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Book Description
Author: R. B. Adamson
Publisher: ASTM International
ISBN: 0803109350
Category : Creep
Languages : en
Pages : 832
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Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124996
Category : Microstructure
Languages : en
Pages : 953
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Author: George P. Sabol
Publisher: ASTM International
ISBN: 0803124066
Category : Nuclear fuel claddings
Languages : en
Pages : 907
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Book Description
Author: A. L. Bement
Publisher:
ISBN:
Category : Zirconium-tin alloys
Languages : en
Pages : 416
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Book Description
Author: D. Lee
Publisher:
ISBN:
Category : Fractures (materials)
Languages : en
Pages : 15
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Book Description
The roles of stress state and crystallographic texture on plastic flow fracture and fracture behavior were examined for Zircaloy-2 sheet specimens irradiated to fluences of 0.7 to 1.9 x 1021 neutrons/cm2 (E > 1 MeV) at 327°C. The extent of strengthening achieved by texture was determined by comparing the level of flow strength obtained under the plane strain loading condition to that of simple uniaxial tension, all at the test temperature of 250°C. It was demonstrated that the relative aspects of texture strengthening were retained in the post-irradiation tests; that is, the material with the peak basal pole density parallel to the sheet normal evidenced less ductility than that with the peak basal pole density inclined at 30 deg to the sheet normal. Supporting evidence is presented in terms of the changes in flow stress and ductility with texture and by the magnitude of R, the ratio of the transverse plastic strains. Plane strain loading increased the flow stress by 66 percent in the material having the peak basal pole density parallel to the sheet normal, but did not change the flow stress for material with the peak pole density inclined > 60 deg to the sheet normal. Texture strengthening persisted to the maximum fluence tested, suggesting a strong texture effect on the mechanical behavior of irradiated materials. The overall level of strain at fracture was substantially reduced by irradiation. The deformation and fracture modes were also strongly affected by texture as well as by the loading methods. The irradiated Zircaloy sheet with the peak basal pole density in the normal direction tended to deform by means of sharply defined deformation bands; intersection of these bands also leads to initiation of fracture. In the other materials (peak basal pole densities inclined to the normal by angles > 30 deg) the deformation bands tended to be more diffuse.
Author: Cyril A. Migdal
Publisher: ASTM International
ISBN: 0803134932
Category : Antioxidants
Languages : en
Pages : 929
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Book Description
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.
Author:
Publisher: Elsevier
ISBN: 0081028660
Category : Science
Languages : en
Pages : 4871
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Book Description
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
Author:
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 1008
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Book Description
