Download or read book Tensile Properties of Irradiated Calandria Tubes at Low to High Rates of Strain written by Randy W. L. Fong and published by Chalk River, Ont. : Chalk River Laboratories. This book was released on 1997 with total page 10 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Programme ctizen high strain rate tensile properties of irradiated zircaloy 2 calandria tube material written by R. W. L. Fong and published by . This book was released on 1995 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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 An Evaluation of Heavy water moderated Organic cooled Reactors written by Oak Ridge National Laboratory and published by . This book was released on 1968 with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The mechanical properties of irradiated calandria tube materials to end of life conditions written by M. K. Y. Ip and published by . This book was released on 2001 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The tensile properties of sixteen calandria tubes written by C. E. Ells and published by . This book was released on 1990 with total page 0 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book AEC Research and Development Report written by Atomic Energy Commission and published by . This book was released on with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Physics and Mechanics of Finite Plastic and Viscoplastic Deformation written by International Symposium on Plasticity and Its Current Applications and published by . This book was released on 1997 with total page 488 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel written by RL. Fish and published by . This book was released on 1976 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt: Tension tests were performed on annealed Type 304 stainless steel specimens sectioned from Experimental Breeder Reactor-II (EBR-II) duct thimbles. The specimens had accumulated neutron fluences of up to 10.3 x 1022 neutrons (n)/cm2, E > 0.1 MeV (10.3 x 1026 n/m2, E x16 fJ). Irradiation temperatures for the material tested ranged from 700 to 750°F (644 to 672 K). The tests were performed at temperatures of room temperature to 1400°F (1033 K), employing strain rates of 2 x 10-3 to 2/min (3.3 x 10-5 to 3.3 x 10-2/s).

Download or read book WASH written by and published by . This book was released on 19?? with total page 292 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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:

Download or read book Tensile Properties of 12 Cold Worked Type 316 Stainless Steel Irradiated in EBR II Under Lower Dose Rate Conditions to High Fluence written by T. Yoshitake and published by . This book was released on 2001 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of lower-dose-rate irradiation on the tensile properties of 12% cold-worked type 316 stainless steel hexagonal ducts which were irradiated in the outer rows of EBR-II were investigated. Tension tests were conducted on a total of seventeen irradiation conditions. Fractographic examinations were performed on four irradiation conditions which were selected based on the results of tension tests. The results of the tension tests and fractographic examinations showed that the 316 stainless steel hexagonal ducts exhibited irradiation hardening typical to 316 stainless steels irradiated at similar temperatures and retained respectable ductility after the irradiation. There was no significant effect of dose rate on tensile properties for the range of irradiation conditions of this study.

Download or read book Proceedings Annual Conference written by Canadian Nuclear Society. Conference and published by . This book was released on 1989 with total page 404 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Irradiation and Thermal Effects on the Tensile Properties of Inconel 718 written by RL. Knecht and published by . This book was released on 1976 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: The effects of neutron irradiation and out-of-flux aging on the tensile properties of wrought and weld-deposited Inconel-718 have been investigated following fast-reactor irradiation to total fluences ranging from 0.55 x 1022 neutrons (n)/cm2 (~400°C) (752°F) to 6.6 x 1022 n/cm2 (649°C) (1200°F) and thermal exposure at 538 and 649°C (1000 and 1200°F) for durations to 10 000 h. Classical irradiation hardening is exhibited by this very strong material following irradiation at low temperature (~400°C) (752°F) to relatively low fluence (~1022 n/cm2) and also at high temperature when very high fluence (6.6 x 1022 n/cm2) is accumulated. At test temperatures >=538°C (1000°F), ductility losses arising from helium embrittlement are evident for all irradiation conditions and at high fluences are so severe as to restrict the strength to lower than expected values.

Download or read book Publications in Engineering written by and published by . This book was released on 1998 with total page 748 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Tensile Property Correlations for Highly Irradiated 20 Percent Cold Worked Type 316 Stainless Steel written by NS. Cannon and published by . This book was released on 1979 with total page 16 pages. Available in PDF, EPUB and Kindle. Book excerpt: Recent experiments on developmental fast-flux test facility (FFTF) cladding (20 percent cold-worked Type 316 stainless steel) have extended the data base to a fast neutron fluence of 8.4 x 1022 neutrons (n)/cm2 (E > 0.1 MeV). The specimens were irradiated in the experimental breeder reactor-II (EBR-II) at temperatures ranging from 371 to 816°C, although peak fluence levels were attained on specimens irradiated near 371 and 649°C only. Tension tests were performed at 232°C, near the irradiation temperature, and, in some cases, above the irradiation temperature. Test specimen strain rates ranged from 4 x 10 -5/s to 4 x 10-2/s.

Download or read book Strain Rate Dependence of the Tensile Properties of V 4 5 Cr 4 5 Ti Irradiated in EBR II and HFBR written by and published by . This book was released on 1998 with total page 4 pages. Available in PDF, EPUB and Kindle. Book excerpt: Elevated temperature tensile tests performed on V-(405)Cr-(4-5)Ti indicate that the yield stress increases with increasing strain rate for irradiation and test temperatures near 200 C, and decreases with increasing strain rate for irradiation and test temperatures near 400 C. This observation is in qualitative agreement with the temperature-dependent strain rate effects observed on unirradiated specimens, and implies that some interstitial solute remains free to migrate in irradiated specimens. Additional strain rate data at different temperatures are needed.