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.
Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
N. J. Olson, C. M. Walter, W. N. Beck
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 134-151
Technical Paper | Fuels for Pulsed Reactor / Fule | doi.org/10.13182/NT76-A31547
Articles are hosted by Taylor and Francis Online.
A reasonably large number (39) of Mark-IA driver fuel cladding failures have been obtained from run-to-failure experiments in the Experimental Breeder Reactor II over the past few years. These experiments were designed to yield failure information for various design variables and to qualify the fuel element design to a burnup limit such that the risk of an end-of-design-life failure was exceedingly small for normal operating conditions. None of the design variables or operating conditions tested had a significant effect on the failure statistics. The failure mode fit the Weibull statistical failure model and is characterized by a burnup threshold of 3.0 at.% maximum burnup (BUmax), which must be surpassed prior to failure. The cumulative failure probability [F(BUmax)] for peak linear pin powers between 6.4 and 8.0 kW/ft and maximum cladding temperatures from 890 to 1050°F can be expressed as Once 3.0 at.% BUmax is achieved, it was also found experimentally that the failure rate could be decreased over a small burnup interval by lowering the power ratings. The Type 304L stainless-steel cladding in-reactor fracture mode for the Mark-IA driver fuel elements is characterized by inter granular crack propagation that originates at the outside surface of the cladding. This mode of failure appears to be assisted by stress corrosion and potentially deleterious grain boundary precipitation. Although the fracture mode is brittle in nature, uniform mechanical hoop strains >1% are achieved prior to failure.