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Book Microstructural Evolution of Martensitic Steels During Fast Neutron Iradiation

Download or read book Microstructural Evolution of Martensitic Steels During Fast Neutron Iradiation written by and published by . This book was released on 1989 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Irradiation of martensitic/ferritic steels with fast neutrons (E> 0.1 MeV) to displacement damage levels of 30--50 dpa at temperatures of 300--500°C produces significant changes in the as-tempered microstructure. Dislocation loops and networks can be produced, irradiation-induced precipitates can form, the lath/subgrain boundary structure and the thermal precipitates produced during tempering can become unstable, and if helium is present, bubbles and voids can form. These microstructural changes caused by irradiation can have important effects on the properties of this class of steels for both fast breeder reactor (FBR) and magnetic fusion reactor (MFR) applications. The purpose of this paper is to compare reactor-irradiated and long-term thermally aged 9Cr--1MoVNb specimens, in order to distinguish effects due to displacement damage from those caused by elevated-temperature exposure alone. 7 refs., 1 fig.

Book MICROSTRUCTURAL EVOLUTION OF MARTENSITIC STEELS DURING FAST NEUTRON IRASIATION

Download or read book MICROSTRUCTURAL EVOLUTION OF MARTENSITIC STEELS DURING FAST NEUTRON IRASIATION written by P.J. MAZIASZ. and published by . This book was released on 1989 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Small Angle Neutron Scattering Study of Irradiated Martensitic Steels

Download or read book Small Angle Neutron Scattering Study of Irradiated Martensitic Steels written by M-H Mathon and published by . This book was released on 2005 with total page 15 pages. Available in PDF, EPUB and Kindle. Book excerpt: Martensitic/ferritic steels (containing 7-13 % Cr) are candidate materials for internal structures in pressurized water, fast breeder, and fusion reactors. Approval for use requires verification of structural stability under neutron irradiation in relation to the evolution of mechanical properties. In this context, several conventional and Reduced Activation (RA) martensitic materials were neutron irradiated at 325°C up to 6 dpa. They were investigated by Small Angle Neutron Scattering (SANS) under a magnetic field after various doses.

Book Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels After Thermal Aging and Neutron Irradiation

Download or read book Microstructural Evolution of Reduced Activation and Conventional Martensitic Steels After Thermal Aging and Neutron Irradiation written by M-H Mathon and published by . This book was released on 2001 with total page 20 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Energy Research Abstracts

Download or read book Energy Research Abstracts written by and published by . This book was released on 1995 with total page 782 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Response of Ferritic Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K

Download or read book Response of Ferritic Martensitic Steels to Neutrons at Irradiation Temperatures from 20 to 823 K written by Hideki Matsui and published by . This book was released on 1990 with total page 18 pages. Available in PDF, EPUB and Kindle. Book excerpt: The objectives of this work are to evaluate mechanical property changes by means of small specimen testing techniques, to evaluate the influence of the cascade damage produced by 14-MeV neutrons from RTNS-II on microstructural evolution, and to understand mechanical property changes in term of microstructural evolution at irradiation temperatures of from 20 to 823 K.

Book Scientific and Technical Aerospace Reports

Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1994 with total page 892 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book High chromium Ferritic and Martensitic Steels for Nuclear Applications

Download or read book High chromium Ferritic and Martensitic Steels for Nuclear Applications written by R. L. Klueh and published by ASTM International. This book was released on 2001-01-01 with total page 221 pages. Available in PDF, EPUB and Kindle. Book excerpt: This monograph reviews the development of high-chromium ferritic/martensitic steels for exposure to the high-energy neutron environment of a fission or fusion reactor, and considers their potential use as a component material. The basic properties of the steels under non-nuclear conditions are provi

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Todd R. Allen and published by ASTM International. This book was released on 2006 with total page 411 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation

Download or read book Influence of Minor Alloying Elements and Stress on Microstructural Evolution and Void Swelling of Austenitic Steels Under Neutron Irradiation written by R. Hübner and published by . This book was released on 2000 with total page 14 pages. Available in PDF, EPUB and Kindle. Book excerpt: A pressurized tube experiment was carried out in the British Prototype Fast Reactor (PFR) at Dounreay, U.K. in order to determine swelling and stress-induced swelling of four heats of the commercial German austenitic steel DIN 1.4970, with different contents of the minor alloying elements Si, Ti and Ti/C ratio. The maximum doses achieved are 106 dpaNRT at 420°C, 81 dpaNRT at 500°C and 61 dpaNRT at 600°C. The hoop stresses of the pressurized tubes were 0, 60 and 120 MPa at all irradiation temperatures. TEM-examinations have been carried out to determine the influence of the minor alloying elements and the stress on the void swelling and the microstructural evolution. All alloys exhibited the highest swelling values at 420°C and no swelling at 600°C. The measurements show the large effect of the minor alloying elements upon swelling and in-pile creep. The maximum swelling suppression is achieved by a high Si-content and an understoichiometric Ti/C ratio (understabilization). The analysis of the microstructural evolution shows that the swelling resistance is correlated to the formation and stability of very fine ?'-precipitates. For the alloy with the highest swelling resistance these precipitates can be found up to 106 dpaNRT at 420°C, whereas they dissolve in the course of irradiation for the alloys with lower swelling resistance.

Book Review

    Book Details:
  • Author : Oak Ridge National Laboratory
  • Publisher :
  • Release : 1992
  • ISBN :
  • Pages : 804 pages

Download or read book Review written by Oak Ridge National Laboratory and published by . This book was released on 1992 with total page 804 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Radiation induced Changes in Microstructure

Download or read book Radiation induced Changes in Microstructure written by F. A. Garner and published by ASTM International. This book was released on 1987 with total page 919 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Stan T. Rosinski and published by ASTM International. This book was released on 2001 with total page 879 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book Effects of Radiation on Materials

Download or read book Effects of Radiation on Materials written by Roger E. Stoller and published by ASTM International. This book was released on 1992 with total page 1315 pages. Available in PDF, EPUB and Kindle. Book excerpt: Symposium held in Nashville, Tennessee, June 1990. Almost two-thirds of these 91 papers are authored by researchers outside of the US (including information on research in the former USSR, Japan, and Europe). Topics include: current commercial power reactor systems; microstructural characterization

Book TMS 2014 143rd Annual Meeting   Exhibition  Annual Meeting Supplemental Proceedings

Download or read book TMS 2014 143rd Annual Meeting Exhibition Annual Meeting Supplemental Proceedings written by The Minerals, Metals & Materials Society (TMS) and published by Springer. This book was released on 2016-12-16 with total page 1152 pages. Available in PDF, EPUB and Kindle. Book excerpt: These papers present advancements in all aspects of high temperature electrochemistry, from the fundamental to the empirical and from the theoretical to the applied. Topics involving the application of electrochemistry to the nuclear fuel cycle, chemical sensors, energy storage, materials synthesis, refractory metals and their alloys, and alkali and alkaline earth metals are included. Also included are papers that discuss various technical, economic, and environmental issues associated with plant operations and industrial practices.

Book Microstructural Effects of Neutron Irradiation on Ferritic martensitic Stainless Steels

Download or read book Microstructural Effects of Neutron Irradiation on Ferritic martensitic Stainless Steels written by Terence Stuart Morgan and published by . This book was released on 1992 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Book An Introduction to Nuclear Materials

Download or read book An Introduction to Nuclear Materials written by K. Linga Murty and published by John Wiley & Sons. This book was released on 2013-08-05 with total page 400 pages. Available in PDF, EPUB and Kindle. Book excerpt: Covering both fundamental and advanced aspects in an accessible way, this textbook begins with an overview of nuclear reactor systems, helping readers to familiarize themselves with the varied designs. Then the readers are introduced to different possibilities for materials applications in the various sections of nuclear energy systems. Materials selection and life prediction methodologies for nuclear reactors are also presented in relation to creep, corrosion and other degradation mechanisms. An appendix compiles useful property data relevant for nuclear reactor applications. Throughout the book, there is a thorough coverage of various materials science principles, such as physical and mechanical metallurgy, defects and diffusion and radiation effects on materials, with serious efforts made to establish structure-property correlations wherever possible. With its emphasis on the latest developments and outstanding problems in the field, this is both a valuable introduction and a ready reference for beginners and experienced practitioners alike.