Corrosion and Failure Characteristics of Zirconium Alloys in High-Pressure Steam in the Temperature Range 400 to 500 C
- 1 January 1969
- book chapter
- Published by ASTM International
- p. 271-285
- https://doi.org/10.1520/stp43833s
Abstract
No abstract availableThis publication has 4 references indexed in Scilit:
- RADIATION-ENHANCED OXIDATION OF ZIRCALOY--2 IN pH--10 LiOH AND pH--10 NH$sub 4$OH.Published by Office of Scientific and Technical Information (OSTI) ,1967
- EFFECTS OF FAST NEUTRON IRRADIATION, FABRICATION HISTORY, AND WATER OXYGEN ON THE ENVIRONMENTAL BEHAVIOR OF ZIRCONIUM ALLOYSPublished by Office of Scientific and Technical Information (OSTI) ,1965
- Zirconium alloys for use in superheated steamJournal of Nuclear Materials, 1961
- The Corrosion of Zirconium Alloys in 900°F SteamPublished by Office of Scientific and Technical Information (OSTI) ,1958