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
Apr 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
May 2026
Nuclear Technology
March 2026
Fusion Science and Technology
Latest News
DOE consortium begins new initiative aimed at growing fuel cycle
The U.S Department of Energy’s Office of Nuclear Energy, through its Defense Production Act (DPA) Nuclear Fuel Cycle Consortium, has begun a new initiative aimed at securing the nation’s nuclear fuel supply chain.
Theodore H. Bauer, John W. Holland
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 407-421
Technical Paper | Actinide Burning and Transmutation Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35110
Articles are hosted by Taylor and Francis Online.
Transient test data and posttest measurements from recent in-pile overpower transient experiments are used for an in situ determination of metallic fuel thermal conductivity. For test pins that undergo melting but remain intact, a technique is described that relates fuel thermal conductivity to peak pin power during the transient and a posttest measured melt radius. Conductivity estimates and their uncertainty are made for a database of four irradiated Integral Fast Reactor-type metal fuel pins of relatively low burnup (<3 at.%). In the assessment of results, averages and trends of measured fuel thermal conductivity are correlated to local burnup. Emphasis is placed on the changes of conductivity that take place with burnup-induced swelling and sodium logging. Measurements are used to validate simple empirically based analytical models that describe thermal conductivity of porous media and that are recommended for general thermal analyses of irradiated metallic fuel.