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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
C. C. Dollins, H. Ocken
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 141-147
Fuel Performance Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28804
Articles are hosted by Taylor and Francis Online.
Current fuel swelling models based upon the growth of fission gas bubbles do not consider effects due to radiation induced re-solution phenomena. This paper describes a fission gas swelling model which assumes that fission fragments will destroy existing gas bubbles and maintain the resulting gas atoms in supersaturated solid solution. Such a model should be particularly applicable to fuels operating at low temperatures and high fission rates. Bubble nucleation and growth then take place until another fission fragment again passes through the same region. Bubble growth is calculated using reaction rate theory over the period of time in which no radiation damage occurs. The model predicts bubble growth significantly smaller than that experimentally determined in UO2. This discrepancy is attributed to assumptions made in defining the re-solution mechanism. The model implies that fission gas bubble growth is a state junction independent of path.