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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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Latest News
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.
Ralph G. Bennett
Nuclear Technology | Volume 96 | Number 1 | October 1991 | Pages 117-122
Technical Note | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A35537
Articles are hosted by Taylor and Francis Online.
Finite element modeling of the stresses in TRISO-coated fuel particles under normal operating conditions is undertaken with the ABAQUS code. Accurate results for the coating layer stresses are obtained with 30 finite elements in the model and ∼100 time steps through the life of the fuel. When compared to an earlier General Atomics/Forschungszentrum Jülich (GA/KFA) computer model of fuel performance, several discrepancies are uncovered in the earlier model. The GA/KFA model underpredicts the stresses in the silicon carbide layer, and the discrepancy increases with fission gas pressure.