Download or read book Investigation of Several Ferritic Steels for High Temperature Service and Their Applicability in Sodium Systems Up to Temperatures of about 600 Deg C written by Jurgen Motz and published by . This book was released on 1967 with total page 11 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Development of Ferritic Steels for High Temperature Sodium Service written by W. C. Hayes and published by . This book was released on 1960 with total page 44 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book List of References on Nuclear Energy written by International Atomic Energy Agency and published by . This book was released on 1967 with total page 1878 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book List of References on Nuclear Energy written by and published by . This book was released on 1967 with total page 1138 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 1975-11 with total page 698 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Compatibility of Ferritic Steels in a Sodium Environment Carburization decarburization at 550 to 700 C written by and published by . This book was released on 1976 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Kinetics of carburization-decarburization of three commercial and two high-purity ferritic steels with chromium and molybdenum contents in the range 9-12 wt percent and 1-2 wt percent, respectively, was studied in a sodium environment at temperatures between 550 and 700°C. Carbon concentration-distance profiles obtained as a function of sodium-exposure time and temperature showed that the steels carburized below 650°C and decarburized at higher temperatures. The carburization-decarburization behavior of the ferritic steels was compared with that of the 21/4Cr--1Mo ferritic and Type 304 stainless steels. Microstructural examination of sodium-exposed specimens revealed that the atom ratio of molybdenum to carbon in the steel had a significant effect on the stability of the carbide structure in equilibrium with the ferrite matrix. Nitrogen transfer from the commercial 9Cr--2Mo steel to the sodium environment occurred at temperatures between 550 and 700°C. (auth).
Download or read book Heat Treatment and Properties of Iron and Steel written by Samuel Jacob Rosenberg and published by . This book was released on 1966 with total page 52 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nanoscale Investigation of High Temperature Oxidation Mechanisms of High Cr Ferritic Steels written by Ashok Vayyala and published by . This book was released on 2020 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Mond Nickel Bulletin written by and published by . This book was released on 1955 with total page 648 pages. Available in PDF, EPUB and Kindle. Book excerpt: Includes sections "Abstracts and references" and "Pattents".
Download or read book Corrosion and Decarburization of the Ferritic Chromium molybdenum Steels in Sodium Coolant Systems written by W. C. Hayes and published by . This book was released on 1958 with total page 38 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Ferritic Steels for High temperature Applications written by Ashok K. Khare and published by . This book was released on 1983 with total page 352 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An Investigation of Three Ferritic Steels for High temperature Application written by Arthur P. Coldren and published by . This book was released on 1957 with total page 107 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Optimization and Testing Results of Zr bearing Ferritic Steels written by and published by . This book was released on 2014 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The mission of the Nuclear Energy Enabling Technologies (NEET) program is to develop crosscutting technologies for nuclear energy applications. Advanced structural materials with superior performance at elevated temperatures are always desired for nuclear reactors, which can improve reactor economics, safety margins, and design flexibility. They benefit not only new reactors, including advanced light water reactors (LWRs) and fast reactors such as sodium-cooled fast reactor (SFR) that is primarily designed for management of high-level wastes, but also life extension of the existing fleet when component exchange is needed. Developing and utilizing the modern materials science tools (experimental, theoretical, and computational tools) is an important path to more efficient alloy development and process optimization. Ferritic-martensitic (FM) steels are important structural materials for nuclear reactors due to their advantages over other applicable materials like austenitic stainless steels, notably their resistance to void swelling, low thermal expansion coefficients, and higher thermal conductivity. However, traditional FM steels exhibit a noticeable yield strength reduction at elevated temperatures above ~500°C, which limits their applications in advanced nuclear reactors which target operating temperatures at 650°C or higher. Although oxide-dispersion-strengthened (ODS) ferritic steels have shown excellent high-temperature performance, their extremely high cost, limited size and fabricability of products, as well as the great difficulty with welding and joining, have limited or precluded their commercial applications. Zirconium has shown many benefits to Fe-base alloys such as grain refinement, improved phase stability, and reduced radiation-induced segregation. The ultimate goal of this project is, with the aid of computational modeling tools, to accelerate the development of a new generation of Zr-bearing ferritic alloys to be fabricated using conventional steelmaking practices, which have excellent radiation resistance and enhanced high-temperature creep performance greater than Grade 91.
Download or read book Conference Papers Index written by and published by . This book was released on 1987 with total page 950 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book An investigation of three ferritic steels for high temperature application written by Arthur P. Coldren and published by . This book was released on 1956 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book High Performance Stainless Steels written by Curtis W. Kovach and published by . This book was released on 2000 with total page 96 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Structural Alloys for Nuclear Energy Applications written by Robert Odette and published by Newnes. This book was released on 2019-08-15 with total page 673 pages. Available in PDF, EPUB and Kindle. Book excerpt: High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
