PHYSICAL CONDITION OF SRE ZIRCONIUM
A cursory examination to determine the effect of SRE irradiation and sodium exposure on the zirconium cladding material was carried out. Chemical analysis, simple bend tests, and metallography were performed on specimens removed from moderator cans. No grain growth occurred at the normal reactor operating temperatures of 500 to 95O deg F. Increases in the oxygen and hydrogen contents to as much as 3300 and 1000 parts per million, respectively, resulted from reactor exposure. The increase in hydrogen content causes the zirconium to be very brittle at room temperature. At approximately 200 deg F and above, the ductility of the SRE-exposed zirconium is similar to that of asreceived material. Except for the addition of surface oxide which could possibly reduce the fatigue life, normal SRE exposure to data had little effect upon the properties of the zirconium at reactor operating temperatures. (auth)
- Research Organization:
- Atomics International. Div. of North American Aviation, Inc., Canoga Park, Calif.
- NSA Number:
- NSA-15-007771
- OSTI ID:
- 4113765
- Report Number(s):
- NAA-SR-Memo-5842
- Country of Publication:
- United States
- Language:
- English
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