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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
Fluor to serve as EPC contractor for Centrus’s Piketon plant expansion
The HALEU cascade at the American Centrifuge Plant in Piketon, Ohio. (Photo: Centrus Energy)
American Centrifuge Operating, a subsidiary of Centrus Energy Corp., has formed a multiyear strategic collaboration with Fluor Corporation in which Fluor will serve as the engineering, procurement, and construction (EPC) contractor for Centrus’s expansion of its uranium enrichment facility in Piketon, Ohio. Fluor will lead the engineering and design aspects of the American Centrifuge Plant’s expansion, manage the supply chain and procurement of key materials and services, oversee construction at the site, and support the commissioning of new capacity.
Ralph O. Meyer
Nuclear Technology | Volume 155 | Number 3 | September 2006 | Pages 293-311
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT06-A3763
Articles are hosted by Taylor and Francis Online.
In late 1993 and early 1994, tests in France and Japan showed that cladding damage in fuel rods with burnups above 50 GWd/ton occurs at much lower energies than in unirradiated fuel rods when exposed to large power pulses. During the last decade, significant additional test results have become available to permit an interim assessment of potential cladding failure in reactivity-initiated accidents (RIAs) in reactors with fuel burnups above 40 GWd/ton, which is generally regarded as high-burnup fuel. These data are summarized, and systematic biases due to atypical test conditions are identified. The magnitude of biases in the fuel enthalpy for failure are estimated to range from -19 to +27 cal/g for the cases analyzed. With these adjustments, a lower bound of the enthalpies for experimentally observed cladding failure is compared with potential enthalpies in pressurized water reactors and boiling water reactors. Based on available information on control rod worths, it is concluded that current operating reactors in the United States are not likely to experience cladding failure during the worst postulated RIAs.