Download or read book Interfacial Segregation in Fast Reactor Irradiated 12 Chromium Martensitic Steel written by TS. Morgan and published by . This book was released on 1992 with total page 12 pages. Available in PDF, EPUB and Kindle. Book excerpt: Interfacial solute segregation has been studied in FV448-grade 12% chromium martensitic stainless steel following fast reactor irradiation to damage levels of 25 and 46 dpa at temperatures of 400 and 465°C, respectively. The technique of field emission gun scanning transmission electron microscopy has been used to measure solute redistribution profiles, with high spatial resolution, across martensite lath boundaries. Significant nickel and silicon enrichments are detected at the lath boundaries. Chromium levels exhibit more complex behavior, with localized enrichment at the boundary itself but depletion in adjacent matrix regions. These radiation-induced segregation eifects imply that martensite lath boundaries act as major point-defect sinks during neutron irradiation. The magnitude of the silicon segregation is greatest at 400°C, whereas nickel and chromiun concentrations are relatively temperature insensitive. The data are broadly consistent with the current understanding of nonequilibrium segregation processes based on solute atom size effects.

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

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:

Download or read book Effects of Radiation on Materials written by and published by . This book was released on 1982 with total page 1246 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Creep Resistant Steels written by Fujio Abe and published by Elsevier. This book was released on 2008-03-14 with total page 701 pages. Available in PDF, EPUB and Kindle. Book excerpt: Creep-resistant steels are widely used in the petroleum, chemical and power generation industries. Creep-resistant steels must be reliable over very long periods of time at high temperatures and in severe environments. Understanding and improving long-term creep strength is essential for safe operation of plant and equipment. This book provides an authoritative summary of key research in this important area.The first part of the book describes the specifications and manufacture of creep-resistant steels. Part two covers the behaviour of creep-resistant steels and methods for strengthening them. The final group of chapters analyses applications in such areas as turbines and nuclear reactors.With its distinguished editors and international team of contributors, Creep-resistant steels is a valuable reference for the power generation, petrochemical and other industries which use high strength steels at elevated temperatures. - Describes the specifications and manufacture of creep-resistant steels - Strengthening methods are discussed in detail - Different applications are analysed including turbines and nuclear reactors

Download or read book Radiation Induced Segregation in High Chromium Ferritic martensitic Steels written by and published by . This book was released on 2012 with total page 380 pages. Available in PDF, EPUB and Kindle. Book excerpt: High Cr ferritic/martensitic (F/M) steels including nano-featured oxide dispersion strengthened steels (NF-ODS) are a candidate material class for advanced fission and fusion nuclear reactor designs. F/M steels have excellent high temperature strength, low swelling rates and the recent developments in NF-ODS steels has improved their high temperature creep performance. A concern for F/M steels is their radiation induced segregation (RIS) response while in-service. RIS occurs when atomic fluxes preferentially couple to point defect fluxes to defect sinks such as grain boundaries (GBs). For F/M steels no conclusive trends or dependencies on the RIS response have been drawn. Interfaces, including grain boundaries and precipitate-matrix interfaces can alter the RIS response. The grain boundary structure could change the point defect interaction at the GB. Changes in the point defect kinetics at a grain boundary could therefore alter the RIS response at the boundary. Furthermore, oxide nanoclusters in NF-ODS steel act as sinks for point defects under irradiation. The surface area and number density of these nanoclusters in NF-ODS steels could alter the point defect fluxes to GBs. Analytical microscopy techniques were conducted to determine the role of grain boundary structure and nanocluster dispersion on the RIS response in irradiated F/M steels. Here, a 9 wt. % Cr model alloy which simulates the structure of commercially available steels and 14YWT NF-ODS alloy was irradiated under numerous conditions. Both alloys were investigated using STEM/EDS and GB misorientation analysis. Experimental results indicate a preferential segregation of Cr to specific GB misorientations in the model F/M steel. Findings in the NF-ODS alloy indicates the stability of nanoclusters within the alloy alters the concentration gradient of the point defects near irradiated GBs. Based on these results, new theories on the role of interfaces in irradiated F/M steels was developed including a rate theory model which accounts for the GB misorientation angle within the RIS model. These theories will stimulate the development of new F/M steels which are highly resistant to RIS while in-service.

Download or read book Metals Abstracts written by and published by . This book was released on 1993 with total page 606 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by Arvind S. Kumar and published by ASTM International. This book was released on 1994 with total page 1319 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Nuclear Energy written by and published by . This book was released on 1996 with total page 478 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Alloys Index written by and published by . This book was released on 1993 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Effects of Radiation on Materials written by H. R. Brager and published by ASTM International. This book was released on 1982 with total page 1250 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book The Modelling of Combined Radiation Induced and Thermal Non Equilibrium Segregation of Chromium in Neutron Irradiated Austenitic Stainless Steels written by CC. Goodwin and published by . This book was released on 1999 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: A model of the radiation-induced segregation (RIS) and thermal non- equilibrium segregation (TNES) at grain boundaries has been established within a phenomenological theory. This model indicates that the magnitude and extent of segregation is dependent upon the formation of solute-point defect complexes that migrate to grain boundaries. Theoretical predictions are made for the TNES and RIS of chromium in austenitic stainless steels for the first time. The results indicate that for TNES, chromium creates a positive binding energy in the complex, and is thus enriched at the grain boundary. For RIS, chromium produces a negative binding energy in the complex, and is thus depleted at the grain boundary. The combined effect of the two segregation mechanisms is discussed in relation to the evolution of the segregation profile exhibited by the grain boundary. The segregation profiles are shown to be illustrative of analytically measured profiles for similarly treated materials.

Download or read book Comportement Sous Irradiation Des Mat riaux M talliques Et Des Composants Des Coeurs Des R acteurs Rapides written by and published by . This book was released on 1979 with total page 454 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Materials for Nuclear Reactor Core Applications written by and published by . This book was released on 1987 with total page 110 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Physics Briefs written by and published by . This book was released on 1993 with total page 640 pages. Available in PDF, EPUB and Kindle. Book excerpt:

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

Download or read book Modeling Radiation induced Segregation in Ferritic martensitic Steels written by Aaron Patrick Selby and published by . This book was released on 2015 with total page 65 pages. Available in PDF, EPUB and Kindle. Book excerpt: As ferritic-martensitic (FM) steels receive increasing interest, due to the development of Generation IV fission reactors and fusion reactors, it is imperative to understand how the metals will behave under irradiation. Of the radiation effects, radiation-induced segregation (RIS) is of particular concern as it can lead to the formation of intermetallic phases, stress corrosion cracking, and other detrimental effects. However, predicting RIS in FM steels is more complex due to the lack of consistent trends in experimental results. Therefore, we developed a program to simulate RIS in FM alloys. By performing a sensitivity analysis of the input parameters, we found the model to be most sensitive to the defect migration energies. Although the general Chromium (Cr) concentration profile appeared to follow that of experiments, the dose dependence and bulk Cr concentration dependence were not accurately reproduced, and it became obvious that the IK model may be too simple and too sensitive to the input parameters to accurately predict all of the effects of the segregation of Cr.