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
$40M investment to spur new nuclear developments in Idaho and Wyoming
On Monday, the U.S. Department of Commerce announced that its Economic Development Administration (EDA) intends to award $31 million to the Intermountain-West Nuclear Energy Corridor (INEC) Tech Hub. The Idaho Advanced Energy Consortium (IAEC), the group that leads the INEC Tech Hub, subsequently announced that matching donations from its stakeholder partners will bring the total investment up to $40 million.
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.