RPS2
Zirconium Production and Technology: The Kroll Medal Papers 1975-2010
Adamson Ronald
Published: 2010
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These peer-reviewed papers cover all aspects of zirconium technology, including history, ore refinement, production, fabrication, mechanical properties, and physical properties. Many of the early papers deal with state-of-the-art ore refinement and Zr production processes, and the later papers with highly sophisticated metallurgical and scientific technologies. Of the 33 medals awarded, 31 have been for work in the commercial nuclear power industry.
This retrospective covers work conducted in the United States, Canada, Japan, Russia, and Western Europe, including, France, Germany, Sweden, and United Kingdom.
The papers include a whole range of zirconium alloy technical topics, including:
• Irradiation effects
• Evolution of the industry
• Product development
• Production
• Corrosion
• Deformation mechanisms
• Basic microstructures
• Alloy development
• Hydrogen effects
Taken overall, the papers provide a comprehensive technical history of zirconium technology and will be of great interest to both young and experienced workers in the field.
Table of Contents
Introduction to the Kroll Zirconium Medal Papers Book
Adamson R.
The Decision to Use Zirconium in Nuclear Reactors
Rickover A.
Towards an Understanding of Zirconium Alloy Corrosion
Cox B.
Zirconium Technology—Twenty Years of Evolution
Lustman B.
Extractive Metallurgy of Zirconium—1945 to the Present
Stephens W.
Anisotropy in Zircaloy
Picklesimer M.
Mechanistic Modeling of Zircaloy Deformation and Fracture in Fuel Element Analysis
Nichols F.
Zirconium Activities in Europe: 1945–1984
Syre R.
Forty-One Years with Zirconium
Mishima Y., Mishima Y.
The Origins of the Discovery of the New Cezus Process for Separating Zirconium and Hafnium by Extractive Distillation
Guerin J., Besson P., Brun P.
The Irradiation Creep and Growth Phenomena
Fidleris V.
Metal Science Aspects of Zirconium-Base Reactor Material Production in the Soviet Union
Nikulina A.
Development of Zirconium—Barrier Fuel Cladding
Armijo J., Coffin L., Rosenbaum H.
Zirconium Alloy Performance in Light Water Reactors: A Review of UK and Scandinavian Experience
Pickman D.
Learning from History: A Case Study in Nuclear Fuel
Robertson J.
Behavior and Properties of Zircaloys in Power Reactors: A Short Review of Pertinent Aspects in LWR Fuel
Garzarolli F., Stehle H., Steinberg E.
Effects of Neutron Irradiation on Microstructure and Properties of Zircaloy
Adamson R.
Understanding Hydrogen in Zirconium
Sawatzky A., Ells C.
Microstructure and Properties of Zirconium Alloys in the Absence of Irradiation
Charquet D.
Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors
Coleman C.
Physical Phenomena Concerning Corrosion under Irradiation of Zr Alloys
Lemaignan C.
Evolution of the Beta-Quench Process: Kroll Medal Award Presentation, 2001
Schemel J.
ZIRLOT™—An Alloy Development Success
Sabol G.
Review of Deformation Mechanisms, Texture, and Mechanical Anisotropy in Zirconium and Zirconium Base Alloys
Tenckhoff E.
In-Reactor Deformation of Zirconium Alloy Components
Holt R.
Microstructure Evolution in Zr Alloys during Irradiation: Dose, Dose Rate, and Impurity Dependence
Griffiths M.
Zirconium Corrosion Resistance: Key to Success of the Methanol Carbonylation Acetic Acid Process
Sanders B.
Explosion Cladding: An Enabling Technology for Zirconium in the Chemical Process Industry
Banker J.
Performance of Zirconium Alloys in Light Water Reactors with a Review of Nodular Corrosion
Franklin D.
The Development of Zr-2.5Nb Pressure Tubes for CANDU Reactors
Cheadle B.
Committee: B10
DOI: 10.1520/RPS2-EB
ISBN-EB: 978-0-8031-8421-3
ISBN-PRINT: 978-0-8031-7018-6
978-0-8031-7018-6
RPS2-EB