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August 24–27, 2026
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NRC public meetings shed light on proposed rules
In the span of just over a week in late June and early July, the Nuclear Regulatory Commission published three proposed rules on modernizing security requirements, low-level radioactive waste disposal requirements, and fuel cycle and materials licensing.
This week, NRC staff led separate virtual public information meetings on each of the proposed rules, providing details to the public on what each one would change.
W. L. Pearl, E. G. Brush, G. G. Gaul, G. P. Wozadlo
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 235-245
Technical Paper | doi.org/10.13182/NT65-A20508
Articles are hosted by Taylor and Francis Online.
Incoloy-800® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1410° F (766° C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems. The corrosion data from the 4000-h heat-transfer tests indicated good corrosion resistance up to at least 1300° F (704° C) metal temperature. A compositionally changed layer developed at the metal-oxide interface. The changed layer depth appeared to be a function of time and temperature of exposure. The descaled weight-loss data for the sheaths operated at a metal temperature of 1100 to 1300° F (593 to 704° C) indicate that greater than 80% of the oxide corrosion product adhered during the first 1000-h exposure, but only about 50% of the total oxidation product remained after 4000 h. The uniform corrosion experienced by the Incoloy-800® when exposed isothermally to 1050 and 1150° F (566 and 621° C) for 10 000h indicates an initially high-corrosion rate that decreases to a lower constant rate within the first 1000 h. An insignificant amount of the oxide was lost to the system.