Server maintenance is scheduled for Saturday, December 21st between 6am-10am CST.

During that time, parts of our website will be affected until maintenance is completed. Thank you for your patience.

Menu
Search
Filters
Close
Menu

99466 CORROSION BEHAVIOR OF STAINLESS STEEL-ZIRCONIUM ALLOY WASTE FORMS

Picture for 99466 CORROSION BEHAVIOR OF STAINLESS
Available for download
Product Number: 51300-99466-SG
ISBN: 99466 1999 CP
Author: Daniel P. Abraham, Lin J. Simpson, Michele J. DeVries, and Douglas E. Callahan
$0.00
$20.00
$20.00
Stainless steel-zirconium (SS-Zr) alloys are being considered as waste forms for the disposal of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The baseline waste form for spent fuels from the EBR-II reactor is a stainless steel-15 wt.% zirconium (SS- 15Zr) alloy. This article briefly reviews the microstructure of various SS-Zr waste form alloys and presents results of immersion corrosion and electrochemical corrosion tests performed on these alloys. The electrochemical tests show that the corrosion behavior of SS-Zr alloys is comparable to those of other alloys being considered for the Yucca Mountain geologic repository. The immersion tests demonstrate that the SS-Zr alloys are resistant to selective leaching of fission product elements and, hence, suitable as candidates for high-level nuclear waste forms. Keywords: nuclear waste, stainless steel, zirconium, corrosion, microstructure
Stainless steel-zirconium (SS-Zr) alloys are being considered as waste forms for the disposal of metallic waste generated during the electrometallurgical treatment of spent nuclear fuel. The baseline waste form for spent fuels from the EBR-II reactor is a stainless steel-15 wt.% zirconium (SS- 15Zr) alloy. This article briefly reviews the microstructure of various SS-Zr waste form alloys and presents results of immersion corrosion and electrochemical corrosion tests performed on these alloys. The electrochemical tests show that the corrosion behavior of SS-Zr alloys is comparable to those of other alloys being considered for the Yucca Mountain geologic repository. The immersion tests demonstrate that the SS-Zr alloys are resistant to selective leaching of fission product elements and, hence, suitable as candidates for high-level nuclear waste forms. Keywords: nuclear waste, stainless steel, zirconium, corrosion, microstructure
PRICE BREAKS - The more you buy, the more you save
Quantity
1+
5+
Price
$20.00
$20.00
Product tags
Also Purchased
Picture for 99451 METALLURGICAL FACTORS INFLUENCING THE
Available for download

99451 METALLURGICAL FACTORS INFLUENCING THE SUSCEPTIBILITY OF NON-SENSITIZED STAINLESS STEEL TO INTERGRANULAR STRESS-CORROSION CRACKING IN HIGH-TEMPERATURE, HIGH-PURITY WATER ENVIRONMENTS

Product Number: 51300-99451-SG
ISBN: 99451 1999 CP
Author: Masatsune Akashi, Guen Nakayama, Hajime Komatsu , Seizaburo Abe
$20.00
Picture for 99465 GALVANIC CORROSION - EFFECT OF
Available for download

99465 GALVANIC CORROSION - EFFECT OF ENVIRONMENTAL AND EXPERIMENTAL VARIABLES

Product Number: 51300-99465-SG
ISBN: 99465 1999 CP
Author: Ajit K. Roy, Dennis L. Fleming, Beverly Y. Lum
$20.00
Picture for 99450 CHARACTERIZATION OF INTERGRANULAR STRESS-
Available for download

99450 CHARACTERIZATION OF INTERGRANULAR STRESS-CORROSION CRACKING INITIATION IN TYPE 304 STAINLESS STEEL USING SCANNING PROBE MICROSCOPY

Product Number: 51300-99450-SG
ISBN: 99450 1999 CP
Author: A.W. Phelps, G.H. Koch, A.K. Agrawal, and M.P.H. Brongers
$20.00
Categories
Industry
Recently viewed
Popular tags
View all

Association for Materials Protection and Performance

© AMPP All Rights Reserved.
Membership Terms of Content Use
Contact Customer Support