EBookClubs

Read Books & Download eBooks Full Online

EBookClubs

Read Books & Download eBooks Full Online

Book Effects of Neutron Irradiation on Precipitation Hardening Alloys

Download or read book Effects of Neutron Irradiation on Precipitation Hardening Alloys written by C. R. Cupp and published by . This book was released on 1963 with total page 19 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of neutron irradiation on age-hardening alloys are of great importance in determining the usefulness of these alloys in reactors and are, in addition, of fundamental interest in determining the basic mechanisms of radiation effects. Most of the work has been on alloys irradiated as supersaturated solid solutions, although some data are available for specimens irradiated in the aged condition. Irradiation can enhance solid state diffusion sufficiently to initiate precipitation or to allow growth of existing precipitates, which can lead to overaging. In addition, precipitate nuclei can be redissolved by neutron irradiation. Either overaging or re-solution will reduce the strength of the alloy and will affect physical properties as well.

Book Radiation Effects in Materials

Download or read book Radiation Effects in Materials written by Waldemar Alfredo Monteiro and published by BoD – Books on Demand. This book was released on 2016-07-20 with total page 464 pages. Available in PDF, EPUB and Kindle. Book excerpt: The study of radiation effects has developed as a major field of materials science from the beginning, approximately 70 years ago. Its rapid development has been driven by two strong influences. The properties of the crystal defects and the materials containing them may then be studied. The types of radiation that can alter structural materials consist of neutrons, ions, electrons, gamma rays or other electromagnetic waves with different wavelengths. All of these forms of radiation have the capability to displace atoms/molecules from their lattice sites, which is the fundamental process that drives the changes in all materials. The effect of irradiation on materials is fixed in the initial event in which an energetic projectile strikes a target. The book is distributed in four sections: Ionic Materials; Biomaterials; Polymeric Materials and Metallic Materials.

Book Effects of Radiation on Substructure and Mechanical Properties of Metals and Alloys

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:

Book Neutron Irradiation Damage in a Precipitation Hardened Aluminum Alloy

Download or read book Neutron Irradiation Damage in a Precipitation Hardened Aluminum Alloy written by K. Farrell and published by . This book was released on 1973 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: A 6061 aluminum alloy target sleeve from the high flux isotope reactor, originally in a precipitation-hardened condition, was examined for neutron radiation damage after exposure to a maximum fast fluence of 9.2 x 1022 n/cm2 (E > 0.1 MeV) and a thermal fluence of 1.38 x 1023 n/cm2 at 60 C (140 F). Voids and a transmutation-produced silicon precipitate were found to cause about 1.1 percent internal swelling; a surface oxide scale contributed additional swelling. Irradiation-induced strength increases were measured at test temperatures in the range 25 to 200 C (77 to 392 F) and are accounted for in terms of the observed silicon precipitate and an associated dislocation structure. There was also a loss of ductility that was most severe at 200 C. The fracture mode appeared to remain transgranular over the range of test temperatures.

Book Symposium on Radiation Effects on Metal and Nuetron Dosimetry

Download or read book Symposium on Radiation Effects on Metal and Nuetron Dosimetry written by and published by ASTM International. This book was released on with total page 419 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Neutron Irradiation in Non fissionable Metals and Alloys

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:

Book NEUTRON IRRADIATION DAMAGE IN A PRECIPITATION HARDENED ALUMINUM ALLOY

Download or read book NEUTRON IRRADIATION DAMAGE IN A PRECIPITATION HARDENED ALUMINUM ALLOY written by and published by . This book was released on 1972 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Report on the Effects of Neutron Radiation on Structural Materials

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:

Book Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels

Download or read book Effects of Neutron Irradiation on Precipitation in Reactor Pressure Vessel Steels written by RG. Faulkner and published by . This book was released on 2005 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several MnMoNi pressure vessel steels with varying Ni, Cu, and Mo contents have been investigated in the irradiated and unirradiated condition. Examination using analytical transmission electron microscopy was performed in order to understand more fully the nature of both the inter- and intra-granular precipitation in these alloys. In particular, attention has been paid to the carbide population, which exists in the material in addition to the copper precipitates, which have received detailed study elsewhere. The most dramatic revelations concern the discovery that fine, intra-granular (10 nm diameter) Fe3C particles are present in these steels, in addition to the normally expected copper-rich precipitates of a similar size. Neutron irradiation increases the volume fractions of inter- and intra-granular precipitation of all phases (Fe3C, Cu-rich, and Mo2C). Neutron irradiation has the least effect in increasing volume fraction in high Ni; high Cu alloys (WV). The effects of neutron irradiation on precipitation rates are greatest in low Ni; high Cu alloys (SG (SH)). Inter-granular precipitation is most prevalent in the high Ni; low Cu material (WF). It is significant that this material contains the least intra-granular fine-scale precipitation. This is probably because the Cu precipitation is minimal. Mo and C have an important influence on the amount of Mo2C phase formed, with large amounts being observed in high Mo-C, irradiated material (SH) (0.48 % Mo). These results are discussed in terms of various models for inter-and intra-granular precipitate nucleation and growth.

Book The Effect of Nuclear Radiation on Structural Metals

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).

Book Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel

Download or read book Effect of Neutron Irradiation on Tensile and Fracture Toughness Properties of Copper Alloys and Their Joints with Stainless Steel written by P. Toft and published by . This book was released on 2000 with total page 17 pages. Available in PDF, EPUB and Kindle. Book excerpt: Dispersion strengthened (CuAl25) and precipitation hardened (CuCrZr) copper alloys are being considered as candidate materials for the first wall and divertor components of ITER. In the present work, the tensile and fracture resistance properties of CuAl25 and CuCrZr alloys and their joints with 316LN stainless steel have been studied in the unirradiated and neutron irradiated conditions. The joints were produced by hot isostatic pressing (HIP) at 960°C for 3 hours at a pressure of 120 MPa. Test specimens of the base materials CuAl25 and CuCrZr alloys and of the joints (CuCrZr / 316LN and CuAl25 / 316LN) were irradiated with fission neutrons in the DR-3 reactor at Risø in the temperature range from 50°C to 350°C to a displacement dose level of about 0.3 dpa (NRT). Tensile specimens of these alloys were tested at temperatures in the range of 50°C to 350°C. Fracture resistance curves were determined using three point bend tests on specimens of the base materials and of the joints. Tensile and fracture toughness results, together with the metallography of the joints will be presented. Implications of these results and the deformation mechanisms will be briefly discussed.

Book Radiation Effects in Reactor Structural Materials

Download or read book Radiation Effects in Reactor Structural Materials written by Myron B. Reynolds and published by . This book was released on 1963 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effect of fast neutron radiation on the impact strength of two precipitation hardening stainless steels has been determined using full-size Charpy V-notch specimens. The brittle-ductile impact transition temperature of type 17-4 PH stainless steel aged at 1100 F was found to increase from approximately room temperature to values above 300 F after irradiation at 545 F to exposures in excess of 5 x 1019 neutrons per sq cm > 1 Mev. The impact strength of doubly aged austenitic type A-286 stainless steel was found to increase from about 30 ft-lb in the unirradiated condition to approximately 50 ft-lb after irradiation.

Book Effects of Radiation on Structural Metals

Download or read book Effects of Radiation on Structural Metals written by Books on Demand and published by ASTM International. This book was released on 1967 with total page 723 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron Annihilation Techniques

Download or read book Effects of Neutron Irradiation and Thermal Annealing on Model Alloys Using Positron Annihilation Techniques written by AT. Motta and published by . This book was released on 2001 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: We present the results of a systematic investigation of neutron-irradiated and thermally annealed Fe-Cu-Ni-P model alloys using positron annihilation spectroscopy (PAS), including lifetime and Doppler broadening techniques, and Rockwell hardness. These alloys were examined in the as-fabricated state, after irradiation at 270° C to 1 x 1019 n.cm-2, and to 8 x 1019 n.cm-2, and after successive post-irradiation isochronal anneals at temperatures from 200 to 600° C. The results can be qualitatively explained by invoking an irradiation-induced microstructure consisting of a combination of small dislocation-type defects or defect clusters (matrix damage) and dense precipitation of fine scale irradiation-induced precipitates. The matrix damage anneals between 350° C and 450° C. The irradiation-induced precipitates also evolve with annealing, but at higher temperatures. The combined effect of high Cu and high Ni concentrations leads to more extensive irradiation-induced precipitation than in cases where either element is missing, whereas the effect of P is less pronounced. We analyze and compare the results with similar measurements performed on irradiated pressure-vessel steels and with other positron measurements on model alloys, reported in the literature.

Book Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen

Download or read book Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen written by RR. Hasiguti and published by . This book was released on 1970 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Several authors have emphasized that aluminum nitride in iron and iron alloys not only lowers the transition temperature but also suppresses the rise of the transition temperature due to irradiation. To clarify the mechanism of the effect of aluminum nitride, structural changes after irradiation and annealing are observed by means of internal friction and electron microscopy. Materials investigated are iron, containing 0.05 wt% Al and 0.01 wt% N with 1 ppm C and a few ppm 0, and iron, containing 0.02 wt% Al and 0.005 wt% N with 10 ppm C and 20 ppm 0. The materials are annealed at 750 C before irradiation and irradiated in the JRR-2 at temperatures of 60 C and up to 1.2x1019 n/cm2, E 1 MeV. Two new peaks in internal friction are found at ~125 C and ~155 C after irradiation. Besides these changes a new type of precipitate is observed by electron microscopy. These precipitates are thin, doughnut shaped disks with a diameter of 0.3 ?m and are considered to be complex defects of irradiation induced point defects, nitrogen, and aluminum atoms. The 125 C peak of internal friction disappears after annealing at 250 C for 30 min; the 150 C peak disappears after annealing at 150 C for 30 min or aging at room temperature for about half a year. Resolution of free nitrogen is observed, but precipitates do not disappear even after annealing at 350 C for 30 min. The precipitates suppress the formation of irradiation induced complex nitrogen defects and irradiation hardening because of the strong effect of aluminum on nitrogen atoms.