Influence Of Chemical Composition On Uniform Corrosion Of Zirconium Base Alloys In Autoclave Tests PDF Download
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Author | : CM. Eucken |
Publisher | : |
Total Pages | : 15 |
Release | : 1989 |
Genre | : Chemical effects |
ISBN | : |
Download Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave Tests Book in PDF, ePub and Kindle
The influence of the composition of Zircaloy-type alloys has been evaluated previously with respect to mechanical properties (1973 International Conference Zirconium in the Nuclear Industry, ASTM STP 551) and to nodular corrosion (1985 International ASTM Conference on Zirconium in the Nuclear Industry, ASTM STP 939). The present study extends this previous work to include uniform corrosion, which is of interest for cladding tubes and spacer grids of fuel assemblies. A variety of ingots with compositions both within and outside of the ASTM specification range for Zircaloy-2 and Zircaloy-4 have been tested. The material was fabricated into strips using a conventional fabrication procedure, which incorporated an intermediate beta quench followed by working and annealing in the upper alpha-range. The alloy elements covered the following ranges: tin: 0.2 to 1.7%; iron: 0.05 to 0.53%; chromium: 0.04 to 1.05%; and nickel: 0.003 to 0.046%. In addition, oxygen, carbon, silicon, and phosphorus were varied over the range of standard Zircaloy contents.
Author | : PT. Finden |
Publisher | : |
Total Pages | : 12 |
Release | : 1989 |
Genre | : Annealing parameter |
ISBN | : |
Download Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the Zircaloys Book in PDF, ePub and Kindle
Previous investigators have reported the separate influences of chemical composition and heat treatment on the nodular and uniform corrosion of zirconium-based alloys. However, many of these compositions lie outside the allowable Zircaloy ranges required by most nuclear fuel specifications. The current study shows that the corrosion performance of the Zircaloys can be optimized by adjusting chemical compositions within current ASTM ranges, and examines the influence of composition on response to heat treatment. It is believed that this approach will yield improved corrosion performance and results in a product that can be introduced for immediate nuclear service application.
Author | : Leo F. P. Van Swam |
Publisher | : ASTM International |
Total Pages | : 781 |
Release | : 1989 |
Genre | : Nuclear fuel claddings |
ISBN | : 0803111991 |
Download Zirconium in the Nuclear Industry Book in PDF, ePub and Kindle
Author | : Craig M. Eucken |
Publisher | : ASTM International |
Total Pages | : 794 |
Release | : 1991 |
Genre | : Nuclear fuel claddings |
ISBN | : 080311463X |
Download Zirconium in the Nuclear Industry Book in PDF, ePub and Kindle
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
Author | : CM. Eucken |
Publisher | : |
Total Pages | : 25 |
Release | : 1991 |
Genre | : Annealing parameter |
ISBN | : |
Download Controlled Composition Zircaloy-2 Uniform Corrosion Resistance Book in PDF, ePub and Kindle
The influence of chemical composition and manufacturing variables on the nodular corrosion resistance (determined by 500°C non-refreshed steam autoclave testing) of controlled composition Zircaloy-2 was reported previously (Zirconium in the Nuclear Industry: Eighth International Symposium, ASTM STP 1023, pp. 334-345.). The present study extends the previous work to include uniform corrosion, which is of interest for cladding tubes and spacer strips.
Author | : Gerry D. Moan |
Publisher | : ASTM International |
Total Pages | : 891 |
Release | : 2002 |
Genre | : Nuclear fuel claddings |
ISBN | : 0803128959 |
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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.
Author | : A. M. Garde |
Publisher | : ASTM International |
Total Pages | : 805 |
Release | : 1994 |
Genre | : Nuclear fuel claddings |
ISBN | : 0803120117 |
Download Zirconium in the Nuclear Industry: Tenth International Symposium Book in PDF, ePub and Kindle
Author | : George P. Sabol |
Publisher | : ASTM International |
Total Pages | : 907 |
Release | : 1996 |
Genre | : Nuclear fuel claddings |
ISBN | : 0803124066 |
Download Zirconium in the Nuclear Industry Book in PDF, ePub and Kindle
Author | : George P. Sabol |
Publisher | : ASTM International |
Total Pages | : 953 |
Release | : 2000 |
Genre | : Microstructure |
ISBN | : 0803124996 |
Download Zirconium in the Nuclear Industry Book in PDF, ePub and Kindle
Author | : Sam Kass |
Publisher | : |
Total Pages | : 42 |
Release | : 1956 |
Genre | : Nuclear fuels |
ISBN | : |
Download The Corrosion Properties of Zirconium-base Fuel Alloys Book in PDF, ePub and Kindle