ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jul 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
September 2026
Nuclear Technology
August 2026
Fusion Science and Technology
Latest News
GAO report describes cleanup progress at Moab Mill Site
A new report released by the U.S. Government Accountability Office states that the Department of Energy’s Office of Environmental Management (EM) has disposed of more than 16 million tons of radioactive and hazardous waste from the Moab Mill Site. While cleanup continues at the Cold War–era uranium ore processing site in southeastern Utah, a plan for the next phase of groundwater remediation is still needed, according to the GAO.
Jerry F. Kerrisk, John O. Barner, Roy L. Petty
Nuclear Technology | Volume 30 | Number 3 | September 1976 | Pages 361-375
Technical Paper | Uranium Resource / Fuel | doi.org/10.13182/NT76-A31650
Articles are hosted by Taylor and Francis Online.
Cladding ovalities or localized oval regions in the cladding have been observed in many advanced liquid-metal fast breeder reactor fuel elements. The occurrence of ovalities can be related to an internal fuel element mechanism, and in particular to a localized nonaxisymmetric fuel-cladding mechanical interaction resulting from fuel cracking and rearrangement. Elastic calculations of the cladding shape in the vicinity of an ovality have been performed using a simplified model of the fuel-cladding mechanical interaction. A comparison between the calculated and measured ovality shapes shows good agreement. The size of ovalities as measured at room temperature has also been related to the size at operating conditions. Both membrane and bending stresses that are associated with ovalities have been calculated. Ovalities observed in advanced fuel elements increase in size with increasing burnup, but are independent of cladding thickness, gap size, and peak linear power. Data from a pair of similar elements with annealed and cold-worked cladding may indicate a significant inelastic deformation associated with ovalities.