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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
Argonne updates: Fuel research and materials lab
Over the past two weeks, Argonne National Laboratory has announced numerous significant advancements being made by its staff to push forward nuclear fuels and materials research. Those announcements include the opening of the new Activated Materials Lab, the development of a new measurement technique, and the application of new artificial intelligence tools.
J. W. Prados, J. L. Scott
Nuclear Technology | Volume 2 | Number 5 | October 1966 | Pages 402-414
Technical Paper and Note | doi.org/10.13182/NT66-A27617
Articles are hosted by Taylor and Francis Online.
A mathematical model for investigating the irradiation behavior of pyrolytic-carbon-coated fuel microspheres has been formulated. The model can be used to study the influence on coated-particle life of a number of design parameters, such as fuel particle density, number of coating layers, and coating thickness, density, and strength. For typical two-layer coated particles, the model predicts two modes of coating failure: 1) failure initiated at the inner coating surface from the combined effects of fuel swelling, fission-gas pressure, and outer coating shrinkage; and 2) failure initiated at the outer coating surface resulting from anisotropic thermal expansion and fast-neutron damage to the pyrolytic carbon structure. To assure long-term irradiation stability, a coated-particle design must incorporate: 1) free volume to accommodate fission gas and fuel swelling; and 2) an outer coating material that exhibits small dimensional changes under fast-neutron irradiation.