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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
L. A. Neimark, J. D. B. Lambert, W. F. Murphy, C. W. Renfro
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 75-88
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31177
Articles are hosted by Taylor and Francis Online.
Two stainless-steel-clad mixed-oxide fuel elements have been examined after irradiation in EBR-II to a burnup of 11 at.%. The comparison of fuel of low oxygen-to-metal (O/M) ratio (1.94 to 1.97) with fuel of high O/M ratio (1.99 to 2.00) indicated significant differences in fuel and fission-product behavior. The lower oxidizing potential of the low O/M ratio fuel generated no attack of the Type 316L cladding. This appeared to be related to the lack of oxidation and migration of fission-product molybdenum to the cladding surface. Carbide precipitation in the cladding also appeared to be a factor in the type of attack that occurred. Cesium, however, was mobile in both fuels. The separation of the fuel and cladding at high burnup is thought to be related to the deposition of Cs-Mo-O at the interface. In the low O/M ratio fuel, in which the molybdenum did not migrate to the interface, the fuel and cladding remained in contact. The diametral change in the low O/M ratio element, however, was less than in the high O/M ratio element, 3.55% compared with 4.60%. This lower deformation is attributed to greater internal swelling accommodation by the more plastic low O/M ratio fuel. The axial migration of cesium in the low O/M ratio element resulted in an apparently nondetrimental reaction with the UO2 blanket and insulator pellets.
