Download or read book The Effect of Neutron Flux on the Mechanical Properties of Aluminum Alloys written by R. V. Steele and published by . This book was released on 1954 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effects of Neutron Flux on the Mechanical Properties of Aluminum Alloys written by R. V. Steele and published by . This book was released on 1954 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Neutron Irradiation on the Mechanical Properties of a 5154 0 Type Aluminum Alloy written by E. Lijbrink and published by . This book was released on 1982 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: A large number of Al 5154-0 tensile test specimens were irradiated in a core position facility of the High Flux Reactor in Petten, the Netherlands. They were withdrawn from the irradiation rig in seven batches with successively higher accumulated neutron fluences. The highest fluences achieved were 5.7 x 1026 n/m2 (E 0.414 eV) and 6.0 x 1026 n/m2 (E 0.1 MeV), which leads to a mean thermal-to-fast flux ratio of 0.95. The irradiation temperature was 360 K ± 10 K. After each withdrawal the material's tensile properties were determined at 293 K, 323 K and 373 K with a calculated strain rate ?? = 1.65 x 10-4/s. At the higher fluences the ductility figures appear to drop with increasing test temperature. Irradiation to a fluence level of 6 x 1026 n/m2 causes the 0.2% flow stress to increase from ~ 100 MPa to ~ 520 MPa and the uniform elongation to drop from more than 20% to less than 1% at the 323 K test temperature. The results of transmission electron microscopy (TEM), scanning electron microscopy (SEM) and light microscopy (LM) confirm that the behaviour of Al 5154-0 conforms to the general model for Al-Mg solid solution alloys obtained from the ORNL experiences with Al 5052-0. The objective of the irradiation program was to monitor the state of embrittlement that was expected to develop in the HFR core box material. The experimental results are representative for the PSF wall of the core box only. Because of the much higher thermal-to-fast neutron flux ratios prevailing in the other three walls, the test data are not directly applicable to these walls. By working out the implications of the basic model, however, it can be shown qualitatively that the ductility in the other walls will not be significantly better than in the PSF wall.
Download or read book The Effect of Nuclear Radiation on Structural Metals written by Frederic R. Shober and published by . This book was released on 1961 with total page 120 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of fast-neutron (>1 Mev) irradiation on the mechanical properties of structural metals and alloys was studied. Although the yield strengths and ultimate tensile strengths are increased su stantially for most materials, the ductility suffers severe decreases. This report presents these changes in properties of several structural metals for a number of neutron exposures within the 1.0 x 10 to the 18th power to 5.0 x 10 to the 21st power n/sq cm range. Data summarizing these effects on several classes of materials such as carbon steels, low-alloy steels, stainless steels, Zr-base alloys, ni-base alloys, Al-base alloys, and Ta are given. Additional data which show the influence f irradiation temperatures and of post-irradiation annealing on the radiation-induced property changes are also given and discussed. Increases as great as 175% in yield strength, 100% in ultimate strength, and decreases of 80% in total elongation are reported for fast-neutron exposures as great as 5 10 to the 21st power n/sq cm. (Author).
Download or read book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys written by and published by ASTM International. This book was released on 1973 with total page 546 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book The Effect of Irradiation on the Mechanical Properties of 6061 T651 Aluminum written by and published by . This book was released on 1992 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m−2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
Download or read book Effect of Irradiation in a Spallation Neutron Environment on Tensile Properties and Microstructure of Aluminum Alloys 5052 and 6061 written by MJ. Borden and published by . This book was released on 1996 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt: The Accelerator Production of Tritium (APT) and the Accelerator Transmutation of Waste (ATW) programs require structural materials which retain good mechanical properties when exposed in a spallation neutron irradiation environment. One group of materials likely to withstand the environment anticipated for these systems is the aluminum alloy series. To characterize this class of materials in a prototypical irradiation environment, Al5052 (Al-2.7Mg) and Al6061 (Al-1.1Mg-0.5Si) in hardened and annealed conditions were irradiated to a fluence of 4.2x1020 neutrons/cm2 at ~100°C in a spallation neutron source. Following irradiation, tensile tests and post-test examinations were performed to determine the influence of irradiation and test temperature on mechanical properties and fracture mode. It was found that, the properties of these two aluminum alloys were not significantly affected by the irradiation exposure conditions examined here. Thus these materials may be acceptable as structural materials for APT and ATW applications. This conclusion is based on limited mechanical properties testing, supported by other information in the literature on the performance of these materials in other irradiation environments.
Download or read book The Effects of Irradiation on the Mechanical Properties of 6061 T651 Aluminum Base Metal and Weldments written by DJ. Alexander and published by . This book was released on 1999 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The aluminum alloy 6061-T651 was a candidate material for several critical components of the proposed Advanced Neutron Source (ANS) research reactor. In order to determine the effects of irradiation on the mechanical properties of this alloy, irradiations have been conducted in the High Flux Isotope Reactor under conditions that are similar to those predicted for the ANS. Compact and tensile specimens of 6061-T651 aluminum were irradiated at a nominal temperature of 95°C to a thermal neutron fluence of approximately 8 x 1026 m-2 (
Download or read book The Effect of Irradiation on the Mechanical Properties of 6061 T651 Aluminum written by DJ. Alexander and published by . This book was released on 1994 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Critical components of the Advanced Neutron Source (ANS) reactor, to be built at Oak Ridge National Laboratory (ORNL), will be fabricated from 6061-T651 aluminum alloy. This alloy has been selected for its favorable neutronic, thermal, and mechanical properties. The effect of irradiation on the tensile properties and fracture toughness has been studied to allow the lifetime of these components to be estimated. Irradiations were carried out in the High Flux Isotope Reactor at ORNL at a temperature of approximately 95°C to a fluence of approximately 1026 m-2 (thermal). Testing was conducted from room temperature to 150°C. The yield and ultimate tensile strengths were increased by irradiation, and the total elongation decreased, but the fracture toughness at 26 and 95°C was not degraded by irradiation, and decreased only slightly at 150°C.
Download or read book Neutron Irradiation Effects in 5xxx and 6xxx Series Aluminum Alloys A Literature Review written by Murthy Kolluri and published by . This book was released on 2016 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: A literature review on highly irradiated 5xxx and 6xxx series Al alloys is conducted to understand the expected changes in mechanical properties of high flux reactor (HFR) vessel material in relation with microstructural aspects beyond the current surveillance data to support the HFR Surveillance Program (SURP). It was found that the irradiation swelling in 5xxx series alloys is not a crucial degradation mechanism. Dislocation damage is expected to reach a saturation limit in both 5xxx and 6xxx series alloys at relatively low fast-fluence values (
Download or read book The effects of neutron irradiation on the dimensional stability structure and mechanical properties of zirconium aluminum alloys written by D. Faulkner and published by . This book was released on 1980 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of Neutron Irradiation in Non fissionable Metals and Alloys written by International Atomic Energy Agency and published by . This book was released on 1962 with total page 232 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effects of High Thermal Neutron Fluences on Type 6061 Aluminum written by CJ. Czajkowski and published by . This book was released on 1994 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The control rod drive follower tubes of the High Flux Beam Reactor are constructed from precipitation-hardened 6061-T6 aluminum alloy and they operate in the high thermal neutron flux regions of the core. It is shown that large thermal neutron fluences up to -4 x 1023 n/cm2 at 333K cause large increases in tensile strength and relatively modest decreases in tensile elongation while significantly reducing the notch impact toughness at room temperature. These changes are attributed to the development of a fine distribution of precipitates of amorphous silicon of which about 8% is produced radiogenically. A proposed role of thermal-to-fast neutron flux ratio is discussed.
Download or read book Effects of High Thermal Neutron Fluences on Type 6061 Aluminum written by and published by . This book was released on 1992 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: The control rod drive follower tubes of the High Flux Beam Reactor are contructed from precipitation-hardened 6061-T6 aluminum alloy and they operate in the high thermal neutron flux regions of the core. It is shown that large thermal neutron fluences up to (approximately)4 x 1023 n/cm2 at 333K cause large increases in tensile strength and relatively modest decreases in tensile elongation while significantly reducing the notch impact toughness at room temperature. These changes are attributed to the development of a fine distribution of precipitates of amorphous silicon of which about 8% is produced radiogenically. A proposed role of thermal-to-fast flux ratio is discussed.
Download or read book Report on the Effects of Neutron Radiation on Structural Materials written by M. Kangilaski and published by . This book was released on 1967 with total page 264 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Effect of Neutron Bombardment Upon the Properties of ASTM Type SA212B Steel written by Melvin L. Bleiberg and published by . This book was released on 1955 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Irradiation Effects on Structural Materials written by Spencer H. Bush and published by . This book was released on 1964 with total page 128 pages. Available in PDF, EPUB and Kindle. Book excerpt:
