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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith
Nuclear Technology | Volume 71 | Number 2 | November 1985 | Pages 445-457
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33697
Articles are hosted by Taylor and Francis Online.
A set of statistical patterns characterizing the conditions for failure of Type 304 stainless steel clad light water reactor fuel is formulated using a 450-assembly cycle data base from the Connecticut Yankee reactor and an information-theoretic (entropy) criterion of pattern formation. The pattern files, consisting of features formulated from output data obtained from the deterministic fuel performance code FCODE-BETA/SS, are partitioned into five failure and six nonfailure patterns. The failure probabilities of the patterns span the 0.17 to 37.47% range, as compared with the data base average of 2.86%. Features that contribute to failure patterns include large swings in the linear power at high burnup, frequent stress cycling at the ridge, and low coolant pH at high linear power. Contributing to nonfailure are low fission gas release, high axial uniformity in linear power, peak burnup, and clad creep strain at the ridge. The feature describing cycling of the linear power agrees qualitatively with previously identified factors contributing to failure of stainless steel clad fuel in the Connecticut Yankee reactor. From an operational standpoint, the fuel failure probability can be reduced by minimizing the number and magnitude of power ramps and maintaining a neutral coolant pH.