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
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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.”
William J. Kovacs, Karl Bongartz, Dan T. Goodin
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 344-354
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33580
Articles are hosted by Taylor and Francis Online.
A Triso-coated particle stress model was used to describe pressure vessel failure in high-temperature gas-cooled reactor fuel particles. Two separate failure modes were treated, namely, category I, which applies to standard particles characterized by a load-bearing silicon carbide (SiC) layer and instantaneous pyrolytic carbon (PyC) and SiC failure, and category II, which applies to particles with a defective SiC layer incapable of supporting a tensile load. Closed-form solutions, which describe PyC and SiC coating layer stresses as a function of irradiation conditions and particle geometry, were adapted to Monte Carlo calculational routines. The PyC and SiC stresses were calculated for a large number (104 to 106) of particles, and particle failure was predicted to occur when the calculated coating layer tensile stresses exceeded either the SiC (category I failure) or PyC (category II failure) fracture lengths. Model predictions are generally consistent with irradiation test results and serve as a useful guide for particle design optimization studies and in-core fuel performance evaluations.