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The Symposium on Zirconium in Nuclear Applications was held 21-24 August 1973 in Portland, Ore., and was co-sponsored by the American Society for Testing and Materials (ASTM) Committee B-10 on Refractory Metals and Alloys and by the Institute of Metals Division, The Metallurgical Society of the American Institute of Mining, Metallurgical, and Petroleum Engineers (AIME). Program planning was done jointly by representatives of the ASTM Subcommittee B10.02 on Zirconium and Hafnium and by the TMS-IMD Nuclear Metallurgy Committee of AIME. J.H. Schemel, AMAX Specialty Metals Corp., presided as the symposium chairman, and H.S. Rosenbaum, General Electric Co., served as the symposium co-chairman. The session chairman and co-chairman included: A.L. Bement, Jr., Massachusetts Institute of Technology; A. Lowe, Jr., Babcock & Wilcox Company; M.L. Picklesimer, National Bureau of Standards; P.L. Rittenhouse, Union Carbide Corporation; D.E. Thomas, Westinghouse Electric Company; J. Wahler, Combustion Engineering, Inc.; and C.D. Williams, General Electric Company.
The terms phase transitions and phase transformations are often used in an interchangeable manner in the metallurgical literature. In Phase Transformations, transformations driven by pressure changes, radiation and deformation and those occurring in nanoscale multilayers are brought to the fore. Order-disorder transformations, many of which constitute very good examples of continuous transformations, are dealt with in a comprehensive manner. Almost all types of phase transformations and reactions that are commonly encountered in inorganic materials are covered and the underlying thermodynamic, kinetic and crystallographic aspects elucidated. - Shows readers the advancements in the field - due to enhanced computing power and superior experimental capability - Drawing upon the background and the research experience of the authors, bringing together a wealth of experience - Written essentially from a physical metallurgists view point
Annotation The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.
The proceedings of the Ninth International Symposium on [title], held in Kobe, Japan, November 1990, address current trends in the development, performance, and fabrication of zirconium alloys for nuclear power reactors. the bulk of the most recent work on zirconium alloy behavior has concerned corr