A STUDY OF THE WEAR AND GALLING OF AUTOCLAVED ZIRCALOY-2 BY VARIOUS MATERIALS
Technical Report
·
OSTI ID:4833685
A study was made to find a means of preventing damage to Zircaloy-2 process tubes by supports on fuel elements in pressurized water reactors. Twenty- four metals and alloys, four graphite grades, and four ceramic materials were tested on autoclaved Zircaloy-2 as prospective support materials. Of the materials tested, low-carbon steels appear to be best for application as fuel element supports. (D.L.C.)
- Research Organization:
- General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
- DOE Contract Number:
- AT(45-1)-1350
- NSA Number:
- NSA-15-031127
- OSTI ID:
- 4833685
- Report Number(s):
- HW-68195
- Country of Publication:
- United States
- Language:
- English
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