A test to determine the susceptibility of Zr-2 clad thermocouples to fretting corrosion in dynamic systems is described. A dynamic test was performed in TF-7 under operating conditions of 300 deg C, 55 to 60 gpm flow, and velocity of 5.6 to 6.2 ft/sec over a period of 1014 hours. No fretting was observed during the test. The use of Zr-2 clad thermocouples embedded in the core of a prototypical fuel element for fouling detection of particulate solids which circulate through the reactor piping system is proposed. (H.G.G.)
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: AT(45-1)-1350 NSA number: NSA-17-016588 OSTI Identifier 4753307 Research organization: General Electric Co. Hanford Atomic Products Operation, Richland, Wash.