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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
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!
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Nuclear Science and Engineering
March 2025
Nuclear Technology
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February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Henry H. Wong, Ertugrul Alp, W. R. Clendening,+ M. Tayal,+, Lloyd R. Jones
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 203-212
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26282
Articles are hosted by Taylor and Francis Online.
The ELESTRES code is a computer code designed to model the behavior of the Canada deu-terium-uranium nuclear fuel elements under normal operating conditions. It models a single element by accounting for the radial and axial variations in stresses and displacements. The constituent models are physically (rather than empirically) based and include such phenomena as fuel-to-sheath heat transfer; temperature and porosity dependence of fuel thermal conductivity; burnup-dependent neutron flux depression; burnup- and microstructure-dependent fission product gas release; and stress-, dose-, and temperature-dependent constitutive equations for the sheath. The finite element model for the pellet deformation includes thermal, elastic, plastic, and creep strains as well as swelling and densification; pellet cracking; and rapid drop of UO2 yield strength with temperature. It uses the variable stiffness method for plasticity and creep calculations and combines it with a modified Runga-Kutta integration scheme for rapid convergence and accuracy. Comparison of code predictions with experimental data indicates good agreement for the calculation of gas release and pellet-midplane and pellet-end sheath strains.
