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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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!
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
B. Rubin, L. Hynam
Nuclear Technology | Volume 2 | Number 6 | December 1966 | Pages 499-504
Technical Paper and Note | doi.org/10.13182/NT66-A27545
Articles are hosted by Taylor and Francis Online.
High-density UO2 fuel pellets in blanket rods of the first Shippingport core show no structural change after depletions to 6.4 × 1020 fissions/cm3. After 1885 days in hot water, corresponding to post-transition corrosion conditions, the Zircaloy-2 tubing shows a mottled appearance and an oxide thickness averaging 2.4µm, predictable from out-of-pile autoclave testing. The hydrogen content of the tubing agrees reasonably well with similar predictions.
